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PHYSICSRESEARCH

ABSTRACTS

INFORMATIONON RESEARCH IN PROGRESS

INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1984

HEALTH PHYSICS RESEARCH ABSTRACTSNo.11

INFORMATION ON RESEARCH IN PROGRESS

INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA, 1984

I . L —

HEALTH PHYSICS RESEARCH ABSTRACTS, No. 11IAEA, VIENNA, 1984

IAEA/HPRA/11

Printed by the IAEA in AustriaJuly 1984

TABLE OF CONTENTS

INTRODUCTION 5

ALPHABETICAL LIST OF AUTHORS 7

LIST OF TOPICS

ABSTRACTS

I. PERSONAL MONITORING. DOSIMETRY. ASSESSMENT OF DOSE TO MAN(INTERNAL AND EXTERNAL) 15

II. OPERATIONAL RADIATION PROTECTION TECHNIQUES. RADIATION LEVELS 61

III. EFFECTS OF RADIATION:

1. External and Internal Contamination. Human Data 732. Studies of Internal Contamination in Animals 853. External Irradiation (Animal Studies and Human Data) 93

IV. ENVIRONMENTAL STUDIES. PATHWAYS AND MONITORING 101

V. ANALYSIS AND EVALUATION OF RADIATION HAZARDS RESULTING FROM

THE OPERATION OF NUCLEAR FACILITIES 135

VI. RADIATION ACCIDENTS 139

VII. EPIDEMIOLOGY OF RADIATION DAMAGE 143

VIII. OPTIMIZATION OF RADIATION PROTECTION 147

IX. MISCELLANEOUS 151

X. RESEARCH PROGRAMMES AND PROJECTS 159

INTRODUCTION

The present issue No. 11 of Health Physics Research Abstracts is the continuation of a series of Bulletinspublished by the Agency since 1967. They collect reports from Member States on Health Physics research inprogress or just completed.

The main aim in issuing such reports is to draw attention to work that is about to be published and toenable interested scientists to obtain further information through direct correspondence with the investigators.The attention of users of this publication is drawn to the fact that abstracts of published documents on HealthPhysics are published eventually in INIS Atomindex, which is one of the output products of the Agency'sInternational Nuclear Information System.

The present issue contains 235 reports received up to December 1983 from the following Member States.In parentheses the country's ISO code and number of reports are given.

ARGENTINA (AR 14)AUSTRALIA (AU 2)AUSTRIA (AT 15)BELGIUM (BE 4)BRAZIL (BR 22)CANADA(CA13)FINLAND (FI6)FRANCE (FR 19)GERMANY, FEDERAL REPUBLIC OF (DE 3)GREECE (GR 3)HUNGARY (HU 4)INDIA (IN 31)ISRAEL (IL 4)ITALY (IT 28)JAPAN (JP 20)MALAYSIA (MY 1)MEXICO (MX 1)NETHERLANDS (NL 13)NORWAY (NO 1)PAKISTAN (PK1)POLAND (PL 7)SOUTH AFRICA (ZA 8)THAILAND (TH 5)UNITED STATES OF AMERICA (US 11)

"HEALTH PHYSICS RESEARCH ABSTRACTS" is sent free of charge, upon request, to governmental andother institutes as well as to individual scientists. Requests for copies should be addressed to:

Radiological Protection SectionDivision of Nuclear SafetyInternational Atomic Energy AgencyWagramerstrasse 5, P.O. Box 100A - 1 4 0 0 VIENNA,Austria

by using t'ie special form which appears at the end of the bulletin.

LIST OF AUTHORS

A

Abe, S.: 163

Adorini, L. : 98

Afghani, I.: 130

Afsar, M.: 130

Afzal, И.: 130

Aidid, S.B.: 127

Aigueperse, J.: 107

Alma^sy, Zs.: 79, 96, 97

Almeida, C.E.V.: 63

Altavista, P.: 80

Altland, K.: 155

Amano, H.: 122

Anguenot, F.: 107

Araújo, A.M.: 27, 154

Asai, K.: 125

Avadhanula, R.: 34

Aziz, A.: 130

В

Balashf.zy, I.: 21, 75

Baldassini, P.G.: 119

Bamben, A.: 19

Bandyopadhyay, T.: 40

Bank, J.: 79

Bapat, V.N.: 113

Baranski, A.: 69

Barendsen, G.W.: 81, 82

Barroetavena, A.: 149

Barthe, J.: 38, 142

Bassani, В.: 98

Bassi, P.: 89, 90

Bastien, M.T.: 108

Basu, A.S.: 89

Baum, J.W.: 57, 58

Bellintani, S.A.: 24, 29

Belloni, P.: 116, 119

Belvisi, И.В.: 80, 90

Bermann, P.: 38

Bertoncello, G.: 80, 97

Bharathan, A.: 67

Bhat, I.S.: 112

Bhatia, D.P.: 48

Bhatt, 8.C.: 42, 43, 44,

45, 46, 47

Bigu, J.: 32

Biramontri. S.: 132

Blondin, M.C.: 108

Boersma, H.: 55

Bonino, A.: 104

Bonino, N. : 19

Borkar, M.D.: H I

Boutet, L.: 141

Bouville, A.: 107

Brarkenbush, L.W.: 56

Brenot, J.: 149

Brits, R.J.K.: 131, 132

Broerse, J.J.: 55, 82,

83, 163

Brondi, A.: 117

Bruno, H.A.: 141

Burger, G.: 55

Busuoli, G.: 49, 50,

51, 52

Buxerolle, H.: 37

Caamano, J.H.: 19

Cagnetti, P.: 117, 118

Calamosca, M.: 89, 90

Caldas, L.V.E.: 25, 31

Calmet, D.: 108

Campos, J.: 19

Campos, L.L.: 27, 30

Cantu, T.A.: 128

Capuano, V.: 80, 157

Castorina, M.; 80

Cavallini, A.: SO, 51

Cecatti, E.R.: 63

Ceruttl, M.: 39

Chadwick, K.H.: 99

Chagarey, J.: 17, 18

Chakraborty, P.P.: 155

Chambers, D.B.: 162

Chameaud, J.: 145

Chandra, В.: 42, 43,

44, 45, 46, 47

Chandramouli, S.: 112

Charmasson, S.: 108

Chartier, J.L.: 39

Chino, M.: 125

Chittaporn, P.: 133, 138

Christensen, G.C.: 130

Ciallella, H.E.: 103, 104

Civolani, 0.: 52

Clark, G.H.: 105

Clemente, G.F.: 116, 119

Colombo, L.: 80

Conte., L.: 80

Coppola, H.: 80, 97, 98

Corley, J.P.: 134

Coulon, R.: 107

Couto, S.L.: 19

Covelli, V.: 98

Cunha, P.G.: 28, 64

D

Daburon, F.: 95

Daraiani, E.: 117

Danali-Cotsaki, S.: 110, 111

Dang, H.S.: 79

Daschil, F.: 20, 21, 22, 75

David, H.: 113

Davis, H.W.: 34

De Baere, G.: 106, 1S3

De Beer, G.P: 164

De Carvalho. J.L.S.: 106. 107

De Jesus, A.S.H.: 132

De Oliveira, A.E.: 106

De Zaiacomo, T.: 68

Delgado, J.U.: 107

Denley, H.: 78

Dosai, M.V.H.: 111

Desrosiers, A.E.: 142

Deus, S.F.: 24, 29

Deworm, J.P.: 161

Dey, N.N.: 111

Dhairyawan, H.D.: 41

Di Majo, V.: 98

Di Matteo, S.: 48

Di Michèle, A.: 98

Di Paola, H.: 80, 97

Di Pietro, S.: 116, 119

Divina, A.: «8

Doria, G.: 98

Dua, S.K.: 66

Dubner, D.L.: 87

Duftschmid, K.E.: 23, 105

Duport, P.J.: 35

Pormignani, H.: 68

Forner, G.: 89

Eapen, C D . : 114

Ella, J.: 34

Endres, G.W.R.: 56, 57

Escribano, T.L.: 104

Essig, Т.Н.: 57

Gaburo, J.C.G.: 24, 29

Garavini, H.: 98

Garg, S.P.: 40

Garus, D.: 131

Gerdingh, R.F.: 34

Geremia, S.A.: 103

Gibson, D.K.: 153

Gimenez, J.C.: 19

Glasbergen, P.: 129

Gomez, J.C.: 103

Gomez Parada, I.: 87

Gordon, A.H.P.L.: 26, 31

Govaerts, P.: 106, 153

Greenstock, CL.: 154

Gregori, В.: 18

Grosicfca, Z.: 138

Grundling, A.: 131

Hunt, H.W.: 145

I

Ichikawa, R.: 163

Imai, T.: 123, 125

Ingrao, G.: 116, 119

Inoue, Y.: 53

Irving, CF.: 71

Ishikawe, H.: 125

Iyer, M.R.: 155

Jacomino, V.F.: 25, 31

Jagielak, J.: 69, 83

Jaiswal, D.D.: 79

Jammet, H.: 141

Jaquish, R.E.: 134

Jarvinen, H.: 162

Facioli, L.M.: 24, 29

Farias, J.T.: 27

Faruq, M.U.: 130

Faust, L.G.: 56, 71

Fehér, I.: 21, 75

Feital, J.C.S.: 27

Félszerfalvi, J.: 150

Fernandez Degiorei, C. : 87

Ferrara, V.: 117, 118

Ferreira Lima, C.A.: 64

Ferretti, О.: 117

Fieuw, G.: 153

Fisher, D.R.: 165

Florou-G«zi, H.: 110

Flury-Hérard, A.: 141

Fontana, F.: 80

H

Hackler, R.: 155

Hadlock, D.E.: 56, 57

Haq, E.: 130

Haridasan, Т.К.: 40

Heidegger, W.: 95

Heikkila, M.J.: 65

Hennen, L.A.: 82, 163

Hernandez, D.: 17, 18

Hickey, E.E.: 142

Hiroyuki, M.: 120, 127

Hizo, J.: 105

Hofmann, W.: 20. 21,

22, 75, 76, 77

Hogeweg, в.: 81

Holler, E.W.: 164

Huber, M.: 95

Huguet, M.R.: 19

Kai, M.: 125

Kairento, A-L.: 35, 36

Kamada, H.: 121

Kanyar, В.: 79, 96

Kasai, A.: 122, 123

Kathuria, S.P.: 89

Kato, S.: 120, 121, 126

Katz, R.: 22, 77

Kawamura, H.: 52, 81

Kenoyer, J.L.: 72

Kentaro, M.: 120, 127

Keverling Buisman, A.S.: 54

Khan, A.H.: 66, 113

Khasnabis, B.H.: 67

Kiefer, H.: 109

Kiss, A.Z.: 150

Kiviniitty, K.: 78

Koblinger, L.: 21, 75

10

Koch, J.: 114, 115, 137

Kofcubu, M.: 120, 121, 126

Koltay, E.: 150

KSteles, G.J.: 79, 96, 97

Kothari, B.U.: 111

Kotrappa, P.: 41, 66

Kowalska, M.: 90

Kretzschmar, J.G.: 106,

153

Krishna, R.T.: 67

Krommer, I.: 79

Kruger, J.: 71, 165

Kruger, P.J.: 71

Kulkarni, V.V.: 111

Kuroamoto, Y. : 53

Kunst, J,J.: 141

Laitano, R.F.: 48

Lakshmanan, A.R.: 42, 43,

44, 45, 67

Las, W.C.: 25, 26, 31

Lautenbach, G.: 54

Leenhouts, H.P.: 99

Lefaix, J.L.Ï 95

Leidner, L.: 109

Lemaire, G.: 96

Lembo, L.: 49, 50, 51, 52

Leppaluoto, J.: 78

Lessard, E.T.: 58

Leuschner, A.H.: 70, 165

Lombard, J.: 150

Lombardi, C : 68, 89

Lorra'.,'•, î: : 39

Lourens, P.G.: 71

M

Haas, J.: 96

Madelmont, C : 108

Mahapanyawong, S.: 132

Halsin, J.R.: 161

Malamut, C : 63

Mancini, C : 98

Marinello, G.: 39

Markham, J.W.: 64

Martin, J.B.: 142

Martonen, T.: 21, 76

Maruyama, T.: 53

Massera, G.: 19

Mastino, G.: 115

Matkar, V.M.: 111

Matsui. H.: 120, 121, 126

Matsunaga, T.: 122, 123

Matsuzawa, H.: 163

Maurício, CL.P.: 28

Medioni, R.: 38

Míílandri, C : 68

Mendes, L.: 63

Menossi, С : 137

Hertens, I.: 106, 153

Metalli, P.: 80

Metivier, H.: 88

Milintawisamai, M.: 132

Miltenberger, R.R.: 58

Miltenberger, R.P.: 58

Mirna, A.: 109

Mishra, U.C.: 156

Monte, L.: 119

Monteventi, F.: 50

More, A.K.: 111

Moriuchi, S.: 124, J25

Morris, A.D.: 71

Morrison, H.: 87

Mota, H.С: 27

Motta, H.C.: 154

Mourgues, M.: 37

Murata, M.: 120, 121, 126

Musolino, S.V.: 58

Muthukrishnan, G.: 67

N

Nagaoka, T.: 124

tlagarajan, P.S. : 48

Naidu, J.R.: 58

Nair, N.B.: 114

Nakamura, Y.: 125

Nambi, K.S.V.: 89, 112, 113

Nanni, H.: 49, 50, 51

Nasman, P.: 78

Nénot, J.C.: 141

Nguyen, V.D.: 65

Nishizawa, K.: 53

Noda, Y.: 53

Noel, L.: 77

Noguchi, H.: 120, 121, 126

Nolibe, D.: 88

О

Oliveira, A.A.: 103

Oudiz, A.: 150

Pacchierotti, F.: 99

Pages, J-P.: 149

Paganin, G.: 115

Pagano, P.G.: 89

Pai, H.L.: 32

Palácios, E.: 137

Papucci, C.: 117

Parkhurst, M.A.: 56

Parroentier, N.: 65, 108,

141, 145

Perussia, A.: 80

Partridge, C.A.: 71

Paulo, G.. 28

Pawlak, A.: 83

Perveen, N. : 130

Petel, M.: 38, 142

11

Petersen, H.CE.: 105

Pfligersdorffer, P.: 22

Phillips, C.R.: 32, 33

Piechowski, J.: 145

Piesch, E.: 109

Pietruszewski, A.: 69, 83

Pietrzak-Flis, Z. : 91

Pillai, K.C.: 111

Pirinen, M.A.: 65

Pohl, E.: 20, 21, 22, 75

Polphong, P.: 132

Pomroy, C : 77, 78

Porkfca, L.: 35, 36

Portai, G.: 38

Pradel, J.: 145

Pradhan, A.S.: 43, 45,

46, 47

Prempirakul, U.: 132

Puricelli, G.: 80

Putter, H.D.: 70

Quintiliani, M.: 80, 157

Raghavayya, H.: 41,

66, 113

Ranger a j an, C : 114

Rao, S.R.: 111

Rativanich, N.: 56, 132

Raut, S.J.: 111

Rebessi, S.: 98

Redding, S.: 131

Remy, J.: 95

Reyes, R.: 137, 149

Ricourt, A.: 65

Righetti, M.: 17, 18

Robeau, D.: 108

Robinson, A.V.: 165

Rodrigues, L.L.C.: 26, 28

Rosa, L.A.R.: 28, 64

Rossman, U.: 155

Rossouw, J.W.: 70, 165

Ruys, P.N.: 55

Rzyski, B.M.: 25, 26,

28, 30

Saebo, A.: 130

Sahasrabudhe, S.G.: 155

Saiki, M.: 163

Saito, K.: 124

Sakamoto, R.: 124

Santaroni, G.P.: 119

Santaconi, P..: 115

Santori, G.: 116

Sarao, R.: 119

Sarkar, P.K.: 40, 67

Sartori, D.E.: 164

Scarpa, G.: 49

Schraube, H.: 55

Sciocchetti, G.: 119

Segado, R.: 137

Sekine, K.: 123

Selby, J.M.: 57, 71, 72

Sermenghi, I.: 49, 50, 51

Shaikh, G.N.: 156

Shamim, M.: 130

Sharma, R.C.: 40

Shinde, S.S.: 47

Shiragai, A.: 53

Shiraishi, K.: 81

Silva, H.A.: 128

Siegers, W.: 161

Soman, S.D.: 113

Somasundaram, S.: 41, 66

Soos» K.: 79

Sordi, G.M.A.A.: 24, 29

Spano, F.: 17, 18

Srivasttva, G.K.: 41, 66,

113

Steinhïualer, F.: 22, 95

Stemmelen, E.: 149

Stern, E.: 156

Stocker, H.: 87

Stoute, J.R.D.: 129

Suarez, A.A.: 26, 28

Sunta, С.И.: 79, 89, 113

Surendran, T.: 40

Surya, R.B.: 67

Suutala, H.: 35

Swinth, K.L.: 72

Szabo, Gy.: 150

Szabo, P.P.: 47

Tadmor, Jacob: 114, 115,

137, 156

Tadolini, V.: 90

Taja, H.R.: 19

Tamba, M.: 157

Tanaka, G.: 52, 81, 163

Tanninen, A.: 35

Tarroni, G.: 68, 90

Thomasz, E.: 17, 18

Thongmitr, W.: 56

Tinkiel, J.: 104

Timarche, M.: 145

Toivonen, M.: 36

Toni, M.P.: 48

Tsutsumi, M.: 124

U

Ueda, T.: 163

Urban, H.: 109

Vaananen, A.: 162

Valdovinos, H.A.: 128

Vallario, E.J.: 56

Van As, D.: 131, 132

Van der Linden, L.W.J.:

55

Van der Stelt, P.F.: 55

Van der Vorst, J.: 129

Van Weers, A.W.: 128

Van Zwieten, M.J.: 82

Vanderborght, В.: 153

Vandervee, J.: 106

Varma, M.N.: 57

Vegst, A.: 63

Venlcataraman, G.: 41

Vergniaud, G.: 108

Visosekas, R.; 39

Viswanathan, S.: 67

Vohra, K.G.: 43

Vulpis, N.: 80

w

Wagner, H.: 109

Wanitsulcsombut, W. : 56

Wasilewska-Goroulka, M.:

91

Watabe, T.: 121

Whitehouse, R.P.: 154

Wigle, D.T.: 87

Witzani, J.: 23, 105

Wood, S.: 132

Worgotter, E.: 95

Yamaguchi, H.: S3

Yanase, N.: 122, 123

Yoshida, K.: 64

Zarucki, R.: 69

Zarnowiecki, K.: 131

Zawanowski, K.: 69

Zettwoog, P.: 150

Zoetelief, J.: 55, 82, 83, 163

Zurlini, G.: 117

Zuur, C.: 83

Zwigt, A.: 55

13

I.PERSONAL MONITORING. DOSIMETRY. ASSESSMENT OF

DOSE TO MAN (INTERNAL AND EXTERNAL)

15

ARGENTINA IAEA/KPRA/No.11

I. T/TULO У SUBTÍTULO DEL PROGRAMA

Cálculo de ef iciencias para la mediciôn de Pu-239 y ftn-241

en pulmón.Evaluaciôn de larecibida por el ser hu-mano.

Riqhetti, 4 . ; Hernandez, D.; Chaaaray, J . ; Spano, P . ; Thcmasz, E.

I, RESUME»

Se présenta una metodologia para determinar los factores de calibraciôn de un detec-tor phos-tfich para la medición de la carga pulmonar de Pu-239 y An-241. Fsta determina-ciôn depende de las dis t intas distribuciones oue pueden tener los contaminantes en lospulmones, siendo entonces necesario contar con una técnica que considere las distribu-ciones más probables.Les métodos expérimentales de calibraciôn reouieren gran cantidad de modelos pulmonares,por Io oue permite obtener ef iciencias para dist intas qeanetrías. Fl modelo matemáticodesarrollado consiste en la aplicaciôn del método Ttonte Cario ai transporte de fotonesen un fantoma heteroqêneo. El fantoma utili2ado, MIFDV, es una representaciôn matemáticadei hembre de referencia definido en las publicaciôn 23 del ICRP {1975). El côdiqo per-mite obtener Ia distribuciÓn espectral de fotones oue inciden sobre e l detector y larespuesta dal mismo para una fuente puntual dei Pu-239 y ftn-241 ubicadas en el centrocada pulroõn.Se desarrollo, ademãs, un método físico enpleandose un fantoma tecido eouivalente Fiandocon fuente de Pu-239 y Ati-241 posicionadas en el centro de cada pulmôn. Fl detector con-siderado es el centellador de INaíTl) de 2,3 itm de espesor y 127 mm de diâmetro de undetector phoswich, colocado en contacte- sobre el esternôn. Ль L-vplementô la electrónicaãsociaâa a l detector en foiroa ta l de analizar unicamente pulsos producidos por e l c r i s -tal de Ша(Т1). Se presentan los factores de calibraciõn obtenidos experimentalmente ycálculos nediante el c6dioo loqrSndose una buena correspondência entre ambos modelos.

5. NOM

Canisi6n Nacional de Energia AtômicaGerencia de PrObecciôn PadiolÓgica y SequridadAvenida dei Libertador 8250Buenos Aires - Arqentina (CP. 1429)

9. ORGANIZACION U ORGANI2ACIONES PATROCINADORAS

9. DUflACION DEL PROGRAMA

Of / ,

A /

10. SITUACtON.

PRQYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCIÓN LIMITADA 0 N0 LIMITADA -INFORME PRESENT ADO PARA PUBLICACION

Whole body counterPu 239, Am 241Lunqsttonte Carlo Method

Detection Efficiency

ARGENTINA IAEA/HPRA/No.11

Modelo de exposition en campos externos de radiación, determi1

naciôn de factores de conversion.

2. TEMA GENERAL

Fvaluaciõn deIa dosis recibida por

el ser humano

Spano, Francisco; Thomasz, Esteban

4. RESUMEN

Se desarrollô un modele de expos. ,оч oue évalua la dosis eouivalente media por Ôr-gano y dosis ecmivalente efectiva en canpos externos de radiaciôn x y para enerqíascemprendidas entre 10 Kev y 10 Mev. El modelo simula el transporte de fotones en un fan-tema antropanorfo heteroqeneo mediante aplicaciôn dei método Monte Cario. El fantomautilizado, MIRDV, es una representaciôn matemática dei nombre de referencia definida enla publicaciõn 23 del ICRU Í1975). Las interacciones de fotonec an el fantoma fueronevaluadas considerandose reacciones de scattering cempton, símulândose Ia abosrciÔn fo-toelêctrica y fomaciôn de pares, mediante el empleo de pesos estadísticos. Los puntosprobables de interacciôn en los distintos ôrqanos fueron determinados de acuerdo a Iatécnica de Coleman. Se discriminaron cinco médios correspondientes a hueso, tejido blan-do, tejido pulmonar, tiroides y aire.Se desarrollõ, ademâs, un modelo físico utilizando un fantoma tecido equivalente Randoy dosímetros termoluminiscentes de LiF y CaF2tDy. Las qeemetrías de mediciôn simuladasson campos paralelos y fuentes puntuales de enerqías cemprendidas entre 100 Kev y 10 Mev,espectros de rayos x y de Ra-226 en condiciones de exposiciôn A/p y p/A. Se presentanfactores de conversion, dosis equivalente media por ôrgano y dosis eouivalente efectivanormalizadas por unidad de exposición en el punto médio dei fantoma en condiciones librede receptor. La correspondência encontrada entre anbos modelos es excelente en todo elranqo de enerqía estudieda-

Comisiôn Nacional de Energia AtômicaGerencia de Protecciôn Radiolôgica y SegaridadAvenida dei Libertador 82501429 - Buenos Aires - Argentina

7. ORGANIZACION и ORGANIZACO* ASQCIAOAS

. DuflAClON DELPrtOGHAMA 10. SITUAClON

PROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCIÓN LIMITADA 0 N0 L IMPADA-INFORME PRESENTAOO PARA PUBLICACION

External irradiationttonte Carlo MethodMathematical modelPhanuansOrgansDose equivalents

00 ARGENTINA IAEA/HPRA/No.11 ARGENTINA IAEA/HPRA/No.11

1. TITULO V SUITITULO DEL PROUftAMA

Deteminaci6n de la distrihuci6n de dosis eauivalente en la

esfera-ICRU en сдароз de fotœes y neutrones.Dos ime tr ia

3. AUTORES O INVESTIGADORES

Spano, Francisco; №anasz, Esteban; Greqóri, Beatriz

4. HESUMEN

Se determina la distribucion espacial de dosis equivalente en un fantcma esféricohaiKxtêneo en carpos externos de radiación x y y en «1 rango de enercrías ccmprendido en-tre 10 Kev y 10 Mev y para neutrones entre l e v y 5 Mev. El fantcma utilizado es una es-fera tejido eauivalente de 30 cm de diâmetro definido en las publicaciones 25 del ICHLJ(1976).Se desarrollaron modelos matemáticos basados en la aplicaci6n del método de Monte Carioque permite obtener Ia distribucion de dosis eauivalente para distintas condiciones deirradiaciôn en funciõn de Ia eneraía dei campo incidente. Las aecmetrías consideradasen este trabajo son campos paralelos y fuentes puntuales monoenerqéticas y espectros derayos x.Se presentan Ia distribucion de dosis eauivalente, dosis eauivalente media en la esferae índice de dosis equivalente profundo norpalizados con respecte a la exposici6n y f luen-cia en el centro de la esfera en condiciones libres de receptor.Para campos de fotones se desarrollõ, ademâs, un modelo físico de exposiciân simulandoseel fantcma ICPIJ mediante una esfera de lucite de 4 mm de espesor de pared conteniendoaqua en su interior. La distribucion de dosis eauivalente se midiô con dosîmetros termo-luminiscentes de LiF y CaP2:Dy encontrândose una buena correspondência entre ambos mode-los.

Ccmision Nacional de Eneraía AtâmicaGerencia de Proteccion Radiolâqica y SequridadAvenida del Libertador 8250Buenos Aires - Arqentina (CP. 1429)

7. OROANIZADON U ORGANIZACIONES A5OCIAOAS

9. DURACtON DEL PROGRAMA 10. SITUACION

PBOYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARAPUBLICACION

Mathematical modelsMonte Cério method

PhantcmsDose EquivalentExternal Irradiation

11. REFERENCIAS DE PUBLICACIONE5 RECENTES DEL MISMQ SECTOR OIMANADAS DEL LABORATÓRIO

Factibílidad del uso de detectores de Ioduro Mercûrico en la

mediciôn de Pu-239 y Am-241 en heridasEvaluacion de la ctosisrecibida por el ser huma-no.

Riqhetti, Miquel; Hernandez, Daniel; Chagaray, Joroe

Se ha desarrollado una metodoloqía para medir Pu-239 y Am-241 en heridas, producidasaccidentatoente al personal durante los trabajos con dichos nucleidos. Debido a la altaradiotoxicidad de estos nucleidos es necesario, para una correcte intervenclôn, locali-zar y cuantificar en forma rápida la actividad depositada.Una sonda aprepiada para realizar este tipo de mediciones debe poseer área sensible pe-ouefia, alta eficiência, buena resolucion y facilidad de traslado.En este trabajo se emplea el HqI2, cuya característica Io hacen apropiado para la cons-truction de esas sondas. En efecto, en ccmparaci6n con los detectores habitualmenteutilizados, cristales de Ша(Т1) о de ICsOrl), los resultados obtenidos con el materialpropuesto denwestran la factibilidad de discriminar los picos de 13, 17 y 20 Kev delPu-239 y una eficiência para 17 Kev de \f. a 2£ veces superior. Estos valores, unidos afondo menor en las distintas reqiones de interés, hacen del ioduro mercûrico el materialmás conveniente para la determinaciõn reouerida.

Б NOMBRE V t -SlAS DE LA O H G A N I Z A C I O N QUE REALI2A EL TRABAJO

Camisíón Nacional de Fneraía AtánicaGerencia ce protecciòn Padiolóqica y SequridadAvenida dei Libertador 8250Buenos Aires - Arqentina (CP. 1429)

10. SITUACION

PROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARA PUBL'.CACION

Pu-239, Am241WaondsHq!.. semiconductor detector


1. TITULO V SUBTÍTULO DEL PROGRAMA

AplicaciÔn de centelladores líauidos bifãsicos a la medición

de bajos niveles de actividad alfa en orina.

Viqilancia

radioloqica individual


Campes, J.Ï Bcnben, A.; Bonino, N. ; Massera, G.

Se compararon distintas mezclas centelladoras mono y bifâsicas para la determina-ciôn de plutonio, urânio y americio para lo cual, se tuvieron en consideraci6n très va-riables principales: a) los volûmenes de muestra a procesar, b) las variaciones reqis-tradas en ei espectro temporal y c) la distribuciôn de altura de pulsos. Se utilizo uneciuipo convencional de centelleo lîouido al eue se le introdujeron modif icaciones elec-tr6nicas para la discrïminaciôn alfa por forma de puise.Los mejores resultados se obtuvieron con dos mezclas extractantes bifSsicas a base deácido di(2 etil hexil) fosfórico (HDEHP) y oxido de tri octil fosftna (TOPO) , los cualespermitieron en presencia de interférantes beta y gamna, la detecciôn alfa con un limiteinferior de 2.2 x 10-3 + 1.1 x 10"3 Bc (60 ± 30 fCi) y una eficiência del 75% en volúme-nes de 10 ml. Mediante la implenentaciôn de técnicas de purificaciôn y separaciôn deurânio, plutonio y anericio, estas mezclas centelladoras permitenla mediciõn selectivacon baio limite de detecciôn.

CcmisiÔn Nacional de Fnerqia AtômicaGerencia de Protecci6n Radiolcoica y SeguridadAvenida del Libertador 82501429 - Buenos Aires - Arqentina

7. ORCANlZACIOM U ORGANIZACIONES ASOCIADAS

8. ORGANIZACION U ОЯСЗ,

9. OURACION DEL PROGRAMA

DE /

A /

10. SITUAOON

PROYËCTO - INVESTI G AC ION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARA PUBLICACION

UrineLiouid scíntillators

Liouid scintillatinq Detí

HDEHP - TOPOAlpha detection


Dosímetrfa biológica para campos mixtos de radíacíóngamma y neutrones térmicos por análisís cromosómico

2 TEMA GENERAL

Dos imetrfa

Gimenez J.C., Couto S.L., Huguet M.R., Caamaflo J.H., Taja M-R.

Con el propósito de estimar dosîs en caso de sobreexposiciones a produetos defisión o en accidentes de criticidad se realiza la cailbraciõn de un dosímetro рогanãlisrs cromosómico para campos mixtos de radiación gamrou y neutrones térmicos.

Las îrradiac[ones se realizan en la columna térmica de un reactor de produc-ciôn e investigacion. La dosimetría física se realiza con dosímetros termoluminis-centes (TLD 600 y 700). La fîjacion de los lînfocitos cultivados se realiza en elpîco de la onda de la primera mitosis (48-50 horas). Cada punto de la curva de cali-bración se estima a partir dei análisis de 500 metafases.

Para cada dos's se determina la frecuencia de deieciones, anillos y dicén-tricos. Paralelamente se realiza una curva de calibracíón con radiaciones gamma deuna fuente de Со-бО aplicando igual técnica de cultivo. Se determina la relacióndosis-respuesta para los neutrones térmicos a partir de Ia diferencia entre Ias cur-vas de calibracíón con campo mtxto y con radíación gamma.

Comisiõn Nacional de ЕпегдГа AtomicsGerencia de Protección Radiológica v SegurídadAvenida dei Libertador 8250Buenos Aires - Argentina

7. ORGANIZACION U OHGANlZACIONES ASOCIADAS

8. ORGANIZACION U ORGANIZACIONES PATROCINADORAS

9. OUflAClON DEL PHûGfl

DE 1 .. . . , 1.S82ОВОЖЮТв - 1NVESTIGACION EN CURSO -

6. OESCRJPTOOES О PALABRAS CLAWE

Dosimetría biológica decampo mixto.DoslmetrTa citogenéttea.Curvas Js calibracióneitogenética.

AUSTRIA IAEA/HPRA/No.11 AUSTRIA IAEA/HPRA/No.11

Animal lung dosimetry for radon daughter inhalation

2. BROAD HEADING

Assessment of Doseto Man (internal).

3. AUTHORS OR INVESTIGATORS

F. DASCHIL, W. HOFMANN. E. PÛHL

4. ABSTRACTOur present knowledge of biological effects caused by inhaled radon decay products inthe human lung is largely based on experiments with different animal species. Althoughmany biological reactions are qualitatively similar in a variety of mammals, dosimetricresults which depend primarily on morphological and physiological parameters can varyquantitatively over a large range.

In order to allow a correct interpretation of these experimental results and theirextrapolation to man, a computer model (ANIMO) has been developed which permits thecalculation of the dose distribution pattern of inhaled radioactive nuclides in so-called "ideal animals". Appropriate scaling factors for morphological and physiologicalparameters of these "ideal animals" were defined as a function of the total body weightassuming that the anatomical structure of the Weibel lung model can be applied to allanimal species. The applicability of this scaling-down procedure was tested with datafrom experiments on the rat lung, showing a solid agreement between these experimentalresults and our model simulations.

Preliminary results of these calculations have demonstrated that the d-=c distri-bution shows significant differences as a function of body weight by increasing theradiation doses in the peripheral airways of the smaller animals. These results mayhelp us to elucidate the still unresolved question of the relevant dose in the humanlung, supporting the concept of a regional dose in the interpretation of lung cancerincidence rather than the application of a mean basal cell dose.

5. NAME AND MAILING ADDRESS OF О FIG A

Division of BiophysicsUniversity of Salzburg

Erzabt-Klotz-Strasse 11A-5O2O Salzburg, AUSTRIA

IZATION DOING THE WO H

в- SPONSORING ORGANIZATIONS)

9. DURATION OFPROGRAMME

FROM: Л/?*TO: 1?/P3

PflOJCOT - RESEARCH IN PROGRESS -PAnTIAL 0П r i N A L ПСРОПТ WITH LIMITCr0 П UNÜMITCD DIDTniDUTIOH - ПСРОПТGUDM1TTCD ГОП PUBLICATION

DESCRIPTORS OR KEY WORDS

lung dosimetry,internal contamination,natural radiationenv ironisent,

radon,modelling.

11. REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

Daschil, F. and Hofmann, W.: The relevance of animal models for radionuclide inhalatioiin man. Proc. Spec. Workshop "Current Concepts in Lung Dosimetry", salt Lake City, USAPNL-SA-UO49 (1983) :95-102. Abstract in: Rad. Res. 91 (1902) :385.

Microdosimetric analysis of radiation effects in lung tissueby inhaled alpha-emitters.

2. BROAD HEADING

Dosimetry.Assessment of Doseto Man (internal).


W. HOFMAHN

4. ABSTRACT

At the cellular level the concept of absorbed dose loses its significance and has to bfreplaced by the corresponding microdosimetrie quantity, i.e. the "specific energy".Specific energy distributions of alpha particles in lung cells and cell nuclei arecaused by four sources of stochastic effects: (1) randomness of nuclide distributionson airway surfaces, ranging from uniform to "hot spot" distributions, (2) biologicalvariability of tissue and cellular structure in different lung regions, (3) statisticalvariations of the number of cellular hits and the respective cellular chord lengths,and (4) random nature ot discrete energy-loss events in microscopic targets.

The basic approach of this microdosimetric analysis is the superposition of com-puter gener a ted alpha particle tracks onto magnified images of randomly selected tissuesections o£ the rat lung with the aid of an image analysis system. The measurement oftrack lengths in cells for a given radionuclide distribution allows us to calculatethe number of cells hit, the multiplicity of cellular hits, and the specific energydistribution in these cells. This information on hit probability and specific energydistribution can be used to assess the number of lethally damaged cells, the number ofmalignantly transformed cells and their spatial distributions.

This dosimetric concept has been applied to the inhalation of soluble radon decayproducts as well as of highly insoluble 239PuÜ2 particulates. Future efforts will focuson the application of these microdosimetric considerations to the assessment of lungcancer incidence in man.

5. NAME A N Ù MAILING ADDRESS OP OR


Erzabt-Klotz-dtrasse 11A-5O2O Salzburg, AUSTRIA

UIZATION GOING THE WORK

7. ASSOCIATED ORGANIZATIONS)

8 SPONSORING ORGANIZATIONS)

9 DURATION OFPROGRAMME

FROM: IP/81TO. тт-hr.

PnOJCGT - RESEARCH IN PROGRESS-AL ПСРОПТ WITH LIMITED

0UBMITTCO TOR PUBLICATION

DF.SCRIPTORS OR KEY WORDS

lung dosinetry,internal coi.tarainatlon,lung cancer,risk assessment,image analysis,track structure,radon,plutonium.

11. REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED PROM THIS LABORATORY

Hofmann, W.: Cellular lung dosimetry for inhaled radon decay products as a base forradiation-induced lung cancer risk assessment. II. Microdosimetric calculations.Radiât. Environ. Biophys. (1982) 20=113-122.

AUSTRIA IAEA/HPRA/No.11

TITLE AND SUBTITLE

Stochastic lung dose models for radionuclide inhalation

in man.

2. ВЯОЛО HEADING

Dosimetry.

Assessment of Dose

to Man (internal).

W. HOFMANN, L. KOHLlNGER+i, F. DASCHIL, I. F E H Ê R + Ï , I. BALASHAZY*', E. POHL

4, ADSTHACT

arge inter- as well as intra-subnect variabilités have been observed in all morphologicaland physiological parameters involved in lung dosiraetry. A case in point is the anatomicalstructure of the lung which is highly asymmetric with randomly varying linear dimensions,branching angles and number of airways. Morphometric data on the human lung were analyzedto define probability distributions of airway diameters and lengths and to study corre-lations among these parameters. Experimental results of deposition studies with cylindricalglass tubes, varying flow rate, particle size, linear dimensions and branching angles con-firmed the applicability of published theoretical deposition equations for straight tubesand provided additional information on deposition at branching sites. The random walk ofaerosol particles during inhalation and exhalation in such a random airway structure wasthen simulated by Monte Carlo methods yielding probability distributions for the depositionfractions in various lung regions.

With this information on random variations of deposition probabilities and geometricdimensions and additional information of the same kind on clearance velocities and basalcell depths, lung dose distributions could be derived instead of single mean values. Allparameters in this stochastic compartment model arc described by truncated lognormalfrequency distributions yielding basal cell dose distributions which can be approximatedin most cases by lognormal distributions. These basal cell dose distributions are ofprimary significance for.the definition of upper limits in radiation protection regulationsand for the correct interpretation of epidemiological data on lung cancer incidence.

Divisior. of Biophysics

university of Salzburg

Erzabt-Klotz-Strasse 11

A-5Q2O Salzburg, AUSTRIA

7. ASSOCIATED аЯОЛМ12АТЮЛ1(5>

Central Research Institute for Physics, Budapest,

Hungary

8 Sf>ON5Ofl)NG ORCANIZATION(S)

Austrian Academy of Sciences

Hungarian Academy of Sciences

9. DURATION OF

PROGRAMME

FROM:.1./.?1

TO: .". / .7

•PROJECT - RESEARCH IN PROGRESS -PARTIAL 0П FINAL REPORT WITH LIMITED0П UHLtMITCD DISTRIBUTION -- ПСПОПТSUDMITTCO ГОП PUBLICATION

lunç dosimetry,internal contamination,radon,modelling,deposition

Hofmann, W.: Dosimetric concepts for inhaled radon decay products in the human lung-Proc. Spec. Workshop "Current Concepts in Lung Dosimetry", Salt Lake City, USA.PNL-SA-11O<19 (19831:37-43. Abstract in: Radiation Research 91 (19821:366.


Investigation of enhanced radionuclide depositionat bronchial bifurcations.

2. 6ИОДО HEADING

Dosimetry.

Assessment of Dose

to Man (internal).

W. HOFMANN, T. MARTONEN

4 ABSTRACT

Particlv deposition experiments were conducted with upper human respiratory tract models

to assess the behaviour of inspired aerosols. The work focused ujrjon quantitatinq depo-

sition of "hot spots" at airv/ду branching sites. Aerosol mass median aerodynam'c diameter:

(t-lMAD) ranged from 1.9 to 1О.6 /am, and insptrrftory flow rates were 15, 30, and GO liters

per minute. Most airway foifurctítions were locations of enhanced deposition with maximumparticle concentrations, in all experim«r^s, iouni in airway generation three (accordingto Weibel's morphology). For submicroi particles theoretical results indicate "hot spots"at bifurcations produced by diffusional transport, rhe range of particle: sizes analysed,therefore, covers the whole spectrum of radioactive particulate matter concerned in theuranium mining and milling industry.

The influence of these initial deposition pattarns together with increased particleresidence times at airway branching sites due to reduced clearance velocities wassimulated by a compartment model. The results of these computations indLcate highlylocalized accumulations oE radionuclidos at bifurcations in lobar and segmentai bronchi-oles. The resultant "hot spots" cause high dosage to epithelial and basal cells inbronchial tissue. Considering the compétitive effeecs of cellular inactivation andmalignant transformation, these sites of highly localized energy deposition can berelated to sites c£ high incidence of bronchial carcinomas in human subjects. Thus, tJiisfinding has important implications concerning the establishment of exposure limits forthe inhalation of airborne radionuclides.

NAME AND MA'LING ADDRESS OF ORGA'


Erzabt-Klotz-Strasse 11A-5O2O Salzburg, AUSTRIA


+)Northrop Services, Research Triangle Park, N.C., USA

SPONSORING ORGANIZATIONS

PROJECT - RESEARCH IN PROGRESS -PARTIAL 0П FINAL ПСРОПТ WIT11 LIMITCO0П UNLIMITED DIDTniDUTIOH—REPORTGUBMITTED ГОП РЫЙИбДТЮМ-1

DESCRIPTORS OR KEV WORDS

lung dosiraetry,internal contamination,

radon,deposition,lung cancer,r i s k assessment

to AUSTRIA IAEA/HPRA/No.11 AUSTRIA IAEA/HPRA/No.11

The contribution of building materials to radon and daughterconcentrations indoors.

2 аяоао HEADING 1Assessment of Dose toMan (internal andexternal)

3. AUTHORS OR INVESTIGATORSHofmann W-, Steinhãusler F., Pfligersdorffer P., Daschil P. and Pohl E.

4. ABSTRACT 226 232

The radioactivity of building materials, particularly their content of Ra, Th and4 0 K , represents the most important component of the indoor natural radiation environment.Two exposure pathways have to be considered: 1) External gamma irradiation, and 2) Internacontamination by inhalation of radon daughters, originating from exhaled radon.

As the first step in the assessment of the indoor radiation risk the concentrations ofnatural radionuclides in a variety of construction materials have been measured by gammaray spectroscopy. Special consideration has been given to the problem of waste recycling,e.g. the use of fly-ash from coal-fired power plants in the cement industry, or of phos-phogypsum produced by the fertilizer industry for plasterboard production.

Internal contamination is mainly determined by the exhalation of radon from the walls.Experiments have been conducted to measure raulti-sided exhalation for selected specimen inan airtight container. These experiments are supplemented by measurements of one-sidedexhalation as a function of the temperature gradient. Radon, thoron and their daughtersare measured by ionization chamber-, filter- and alpha spectroscopy techniques.

Based on the results of the above measurements a multicompartment model will be deve-loped to study time-dependent changes of radon and daughter concentrations in room air.These simulations will run on a hybrid computer system which facilitates parameter vari-ations, such as exhalation rate, ventilation rate, deposition on surfaces, and meteoro-logical variables.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

Division of Biophysics, University of Salzburg

Erzabt-Klotz-Strasse 11A-5O2O Salzburg / Austria

7, ASSOCIATED ORGANIZATION!^

8. SPONSORING ORGANIZATIONS)

"Fonds zur Fõrderung der wissenschaftlichen Forschung"

and "Bundesministerium für Bauten und Techmk", Austria

FROM:-TO.

- RESEARCH IN PROGRESS -

6 DESCRIPTORS OR KEY WQR

natural radionuclidesbuilding materialindoor exposuregamma spectrometryexhalationcompartment modelradonthoron

Hofmann W.: Strahlenbelastung durch Radon und seine Kerf^llsprodukteWohnraumer,, Proc. ÕSRAD meeting 19R1, Bl-9'1 (1981)

1. TITLE ANDSUBTITLE

A track structure approach toat envirnnmtíntal dose levels.

radiatiun carcmogenesisDijsimetry.

3 AUTHORS OR INVESTIGATORSW. HOFMANN, R. KATE"1")

ABSTRACT

In must cases of radiation exposure of the general public, nr of occupational exposureof the individual, man is exposed to low levels of ionizing radiations. VJ& speak oflow doses when biological targets, such as cells or cell nuclei, are traversed only bysinqle charged particles and their associated delta rays, and where interaction can beneglected. The low desp problem thus reduces to one of understanding the structure ofa particle track for the observed biological end-point, e.g. radiation-inducedcarcinogenesis.

The simultaneous operation of cell killing and transformation, with similar pat-terns of response, suggests strongly that there is a LET window for cancer induction.At the lowest LET's, the probability for malignant transformation is negligible small.At the highest LET's, the probability for survival is negligible small. The jointprobability is highest for fast alpha particles, thus emphasizing the significance ufincorporated alpha-emitters in radiation protection.

A track strucCure interpretation of epidemiological data on cancer incidencesuggests that the linear extrapolation to low doses is invalid. This hypothesis thatcancer induction is з "many-hit" process was tested with the observed lung cancerfrequency in uranium miners caused by inhaled radon daughters. If we plot the excess

lung cancer risk per working level month WU4) vs. the cumulative exposure in WLM,

then the best fits were obtained by a quadratic or cubic dose response function,

revealing that lung cancer induction by alpha particles is a two- or three-hit

mechanism-

5. NAME AND MAILING ADDRESS OF ORGANIZATIONDivision of Biophysics

University of Salzburg

Erzabt-Klotz-Strasse IIA-r>020 Salzburg, AUSTRIA

3 O I N G T

7. ASSOCIATED OKGANIZATIONIS1

University of Nebraska-Lincoln. NE, USA

б SPONSORING ORGANIZATIONS

Max Kade Foundation ana U.S. Department of Energy


FROM 1 0 ' B}TO —-/-"

PnOJCCT - RESEARCH IN PROGRESS -PAfíTtAL 0П FINAL ftEPORT-WITII LI'HITCB0П UNLIMITED DlOTniBUTlON - ПСРОПТ0UDM1TTCD ГОП PUBLICATION


dosimetry,lung cancer,risk assessment,track structure,epidemiology,internal contamination,natural radiation

environment

Hermann, W. and Kata, t . : Track structure analysis of radiation carcinogenesis at low

5озеч.~"РгТх:. 4r.h Sypip. "n Micr^dcsimetry, Jul ich, FRG, 1982. Comm. of the Europ.

Олшшп.. Чер, E U R ; ; ' ^ (1ГГЗ) ;5CS-57T.


1. TlTJ.1 ANO SUBTITLI

Improved Ioni2ation Chamber System for IndoorExposure Measuremen t

Personal Mom-toring -Dosimetry.Assessment of Dose toMan.

лиТиОМ ОЙ INVCST1GA.TOR3

К-E. Duftschmid, J . Witzani

4. AUTIUC?The aim of the project is t-.he development and testing of a largeionization chamber with 120 1 sensitive volume operated at normalatmospheric pressure made from nearly air equivalent plasticsmaterial. The wall thickness of 5 mm (0,45 g/cm

1 ) is sufficient for

secondary electron equilibrium up to several MeV. Due to a thininternal layer of higher atomic number material the wall absorptionfor low energy photons is compensated. In this way an energy responseof + 2 % in the range of 30 keV - 1,25 MeV is obtained, much superiorthan present high pressure ionization chambers. With our digitalcurrent integrator environmental doserates in the order of 0,1 uSv/h(10 uR/h) can be measured with a standard deviation of î nSv/h (0,1 uR/h)within 1000 s integration time. The instrument is useful particulanlyfor measurement of spacial indoor exposurevariations. Measurementsin three different test buildings of well defined construction material(wood, concrete and bricks) and a comparison with the results ofTLD exoosure - and TE-foil Radon measurements showed good agreement.

S> NAMf AMO MAltJNC АЗОЯШ O* OACiM^TiON QQIMC ТнС <"C

Austrian Research Center Seibersdorf

Lenaugasse 10A-T082 Wien

CF2S

9. QU*ATfGM O '••OC»AUM(

FROM: 1 . 8 2 .TO: 1 2 . 8 4

Development of Prototype Systein Final Stage. Long-termtest in progress.

Indoor Exposure.Environmental DosimetryIonization Chamber.

tsï

И. 4f*tfltMCtS Q* MCZNT "UIUICATIQNS IN 5*M| «teus issuta и д и тмц .AIOAATSOV

1 ) D U F T S C H M I D K . E . , H I Z O J . , W I T Z A N I J .

"Automated Dosimetry System for Calibration of Radiation ProtectionInstruments at Low Dose Rates"Proc -Third Intern . Sym., Inverness, Juni 1992


A Fast Automated TLD Calibration System2. »AO*O HUOINC

PersonalMonitoring.

3. * U T H Ç « OR INVtïTIGATOft}

K.E. DUFTSCHMID

The design and application of an automated calibration deviceconsisting of a pneumatic rabbit system with circular irradiationgeometry is described. Four gamma-radiation sources up to 3,7 TBq(100 Ci) 137 Cs are stored in a revolving shielded container. The rabbitscontaining the sources travel through a bent lucite tubing down to anadjustable mechanical stop at the irradatiation position. A flat circularsegment is mounted in 1 m distance. The source position can be adjustedto the center line of the dosemeters which are clamped behind luciteholders for fast and accurate positioning and secondary electronequilibrium. Up to 200 TLD cards can be exposed at once with theirradiation time controlled by an electronic clock. Frequent dosemeasurement with secondary standard îonization chambers proved areproducibility of exposure better than + 0,5 % (2 sigma) for 5 minutesor more irradiation time.

The automated calibration system hss been routinely applied for fast,accurate and convenient calibration of over 50.000 TLD's up to nowused by our personnel monitoring service.

S. NAU| ANO MAit-IMC лЭЭАХи О* O^JWtkTiON OOINC TM£ «OUÏ

Ausfcrian Research Center Seibersdorf

Lenaugasse l0A.1082 Wien

7. ASSOCIATED

FROM:TO:

1 .8212.83

Complete production unit ofcalibra tri on system in routineoperation.

Automated TLD System-.Calibration.Panoramic ExposureUnit.

DUFTSCHMID K.E., "The automatic/computerized TLD-personnel monitoring

system in Austria", 6th Intern. Conf. on Solid State Dosimetry,

Toulouse, April 1980

BRAZIL IAEA/HPRA/No.11 BRAZIL IAEA/HPRA/No.11

TITLE AND SUBTITLE

Determination of Radlonuclides in urine and blood

2 GROAD HEADING

Personal Monito-r ing.Dosimetry- Assesment ofDose to Han (internal andexternal)


S.A. Se l l i n t an i , J.C.G. Gaburo and G.M.A.A. Sordi

4. ABSTHACT

Methods of Analysis of nuclides (Unati 3H, 1 3 ll) e F~ estable In urine e Pb estable in

blood of persons that might be contaminated by these sources of radiation were develop

at the Instituto de Pesquisas Energéticas e Nucleares (IPEN). The aim of the work is to

verify a possible internal contamination and a suitable control. The techniques the

amount of uranium by fluorimetry, tritium by liquid scintillation, iodine-131 by

Nal(Tl) scintillation counter, Fluor by specific ion electrode, lead by atomic absorp-

tion spectrometry are already used routinely to monitor people working at the IPEN and

other tnstitutios and Industries. The quantitative determination of thorium by

activation analysis and plutonium by alpha spectrometry were been developed in I983 and

will be put on routinely in 198*».

In 198^ we will be developing methods for the determination of cesium and strontlon in

biological materials.

5. NAME AND MAI1.<NG ADDRESS OF ORGANIZATION DOING THE WORK

Instituto de Pesquisas Energéticas e Nucleares-IPEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 110*i9 - PinheirosSão Paulo - Brazil

7. ASSOCIATED ORGANIZATION^!

8 SPONSORING ORGANIZATIONS!

9 DURATION OF

PROGRAMME

6. DESCRIPTORS OR KEY WORDS

- Bioassay

- biological testing

- Contamination Regulations

Chemical Analysis

- lodine-13'

PJutonium-233

Thorium-232

Tritium

Lead

Fluorine

Ces íum

Strontium

1 TITLE AND5UBTITLÊ

The Development of a New Mathematical Phantom Representing

Closely the Adult Human for use in Internal Dose Calculation

2. BROAD HEADING

Personal Moni to-ring.iDosimetry. Assessment ofDose to Han(internal andexternal)

3 AUTHORS OR INVESTIGATORS

Leila M. Facioli and Sudernaique F. Deus

A method for the calculations of absorbed dose from internally distributed radionucli-des in the human body makes use of the concept of "specific absorbed fract ion" definedas the fraction of photon energy err. i t ted from the source organ that is absorbed by thetarget, per unit mass.The interation of radiation with matter occurs mainly by photoelectric ef fect , Comptoriscattering and pair production. For each one of these processes the absorptioncoefficients depends on radiation energy. Furthemore, t h ; spatial distribution of thescattered radiation and consequently the scattered energy inside the scatterer w i l ldepend on the type and mass of materials and on their shapes.Having this in mind a new mathematical model which represents closely the adult humanis being developed for use in internal dose calculations.The specific absorbed fractions for the region which represents the head and neck ofthis new model have been obtained by Monte Carlo techniques for discrete energiesranging from 0.010 MftV to I4.O MeV, considering the thyroid as the source organ.The rat io of the specific absorbed fractions in the organs and regions of the head ofthe model developed in this work, relative to the Snyder's model, ranged from 0.66 toI5.9I in the photon energy above considered.

5 NAME AND MAILING ADDRESS OF ORGANIZATION DO'NG THE WORK

Inst i tuto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 110^9 - PinheirosSão Paulo - Brazi1

ASSOCIATED OHGANIZATIt

iPONSORING ORGANIZATiONISi

FROM 06/82TO 08/ 8M

10. STATE OF ADVANCEMENT

Я - RESEARCH IN PROGRESS -

Phantoms, mockup, structural

model, radiation doses, in-

ternal i rradiat ion, dosime-

t r y , contamination.

BRAZIL IAEA/HPRA/No.11

"Radiation Detectors Calibration Development of a

Calibration Laboratory"

2 BROAD HEAOING

Dosimetry

Calibration

Linda V.E. Caldas, Wanda C. Las and Vanusa F. Jacomino

4. ABSTRACT

The main objective of this work is to complete the calibration laboratory, establishintstandard radiation fields for calibration of radiation monitors used in radiologicalprotection and therapy levels. Availabe are low and high activity sources of Ъ0Со andl 3 7Cs, a beta secondary standard set-up (90Sr + 90Y, ZOUT1 and ltt7Pm) and a lowenergy X-rays unît (60 kV). Calibration services are carried out in both radiologicalprotection and therapy levels. To complete this calibration laboratory, a high energyX-reys unit ïs needed; :ince many years we are trying to get an used one by donation,without success. Presently measurements are being made with free air chambers forX-rays, in order to determine their parameters for future use in the calibration andnational intercomparisons, together with our other secondary ionization chambers.

Instituto de Pesquisas Energéticas e Nucleares-IPEN/CNEN/Divisão de Monitoração PessoalCaixa Postal - 110Л9 - PinheirosSão Paulo - Brazi1

8. SPONSORING ORGANIZATION^)

FROM 01/81TO- 12/ 85

10 STATE OF ADVANCEMENTШ Х Ш К - RESEARCH IN PROGRESS -ншттан*ях£шиккакш№^ш

Ca'ibrationSecondary StandardîzatîofRadiation Detectors


"Thulium doped Lithium Tetraborate-Production, Determinationof Dosimetrie Properties, Application"

Dosímetry


Rzyski, B.M.

^O-.'Tm was fused and polycrystall ire powder or glass sheets were produced. The powed we;

compacted in pellet form, sintered and it were determined the sintered pellets TLO

characteristics : TL sensitivity, dose vs. TL response, photon energy dependence,

reusability, fading etc.

Glass sheets were used to study some optical characteristics as: optical absorption

and fluorescence - Тт^+ valence changes by irradiation and the reversibility of the

process.

5. NAME AND MAILING ADDRESS OF ORGANIZATION OOING THE WORK

I n s t i t u t o de Pesquisas Energéticas з Nucleares - IPEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 110*19 - PinheirosSao Paulo - Brazi1

ASSOCIATED OBGAÍ

8. SPONSORING OF.GANI2ATION(SI

1PEN

9 DURATION OF

FROM. / .TO- . / SUBMITTED FOR PUBLICATION

6 DESCRIPTORS OR KEV WORDS

- Lithium tetraborate

- Optical absorption

- Glass

- Thermoluminescence

characteristics

- Fluorescence

- Photon energy dependence

- Sintered pel lets

- Rzyski, B.M. and Morato, S.P. - 55-D.l.Ц.-proceedings 3^th Congress SBPC, Campinas,SP-, Brazil, 1982.

- Rzyski, B.M. and Morato, S.P. - 56-D.1.9.-Proceedings 3*ith Congress SBPC, Campinas.S.P., Brazil, 1982.

" Others submitted ^____

to BRAZIL IAEA/HPRA/No.11 BRAZIL IAEA/HPRA/No.11

High exposure dosimetry using EPR

2. BROAD HEADING

Dosimetry

I

A.H.P.L. Gordon and W.C. Las

4. ABSTRACT

CaSO.:Dy (0,1 % mol) produced In our laboratory is being Investigated as a probable

candidate for dosimetry In the range of high gamma radiation exposure (60 - 16 x 103

C/kg or 2-3 x 105 R - 6.3 x 10' R) using the Electron Paramagnetic Resonance (EPR)

technique. The CaSO^Dy crystals are anhydrous and X-ray diffraction showed orthor-

homblc structure. The crystals were ground into powder and annealed at 600°C for one

hour. The EPR spectrum of single crystal CaSOi:Dy Is reported elsewhere ' . Powder

CaS0Y:Dy between 3 mm lucite was submitted to different exposures of gamma radiation.

fn the range mentioned above, and preliminary results indicated that the amplitude of

an EPR signal at g » 2.003 is linearly proportional to exposure suggesting EPR as a

possible technique for high exposure dosimetry,


Instituto de Pesquisas Energéticas t Nucleares - 1PEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSio Paulo - Brazil

7. ASSOCIATED ORGANIZATIONS!


CNEN

9. DURATION OffROGRAMME

FROM:'. ./.158ЗTO: .. / .1.986

ХЯХОДЯХ- RESEARCH IN PROGRESS -

мжхмэопштгашмххжххиишмх

6. DESCRIPTORS OR KEY

-Electron Paramagne

Resonance

-Dostmetry

-High Exposure

WORDS

ic

1 1 . REFERENCES OP RECENT PUBLICATIONS IN SAME FIELO ISSUED FROM THIS LABORATORY

A.H.P.L. Gordon e W.C. Las - Estudos da linha isotrâpica de RPE em g = 2.002 em

monocrîstais de CaSO iDy - Supl- Ciência e Cultura, 3*» (7 ) , 267 (1982).

1. TITLE AND SUBTITLE

"Manganese Doped Lithium Fluoride - Sintered Pellets"

IROAD HEAOING

Personal Mon Ito-

ring Dosimetry

3, AUTHORS OR INVESTIGATORS

Suarez, A.A.; RzyskI B.M.; Rodrigues L.L.C.

The following radiation dosîmetric characteristics of the TLD LiF:Mg, Ti sintered

pellets manufactured by IPEN'CNEN/SP were studied: TL sensit ivi ty, doses vs. TL

response, photon energy dependence, reusability* fading.

Other characteristics are being evaluated.

NAME AND MAILING ADDRESS OF ORGANIZATION DOING T H E WORK

Instituto de Pesquisas Energéticas e Nucleares * IPENDivisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSão Pauto - Brazf1

7. ASSOCIATED ORGANlZATI

5 ORGANIZATIONS)

CNEN


FROM 0ÍÍ/ S3

TO. 12/ЙЗ

ШШМЯИхиюсиккхвл FINAL REPORT «кетюмиео;

шюиюгакмлтаххишиюгхкккввоииониш

6 DESCHlPTORS OR KEY WORDS

- Fluoride Lithium

- Thermoluminescence

- Personal monitoring

- Sintered pellets

- Photon energy dependence


TifLE ANO SUBTITLE

Development of a CaS0,:0y Dosimeter

2 BROAD HEADING

Persona 1 Mon i to-

ring Dosimetry


Le t i c Га L. Campos

4. ABSTRACT

Polycrystalline pellets of a cold pressed'mixture of CaSO^tDy and NaCl powders was develo_

ped and studied with the purpose of obtaining a personal thermoluminescent (Tl_) dosimeter

for radiation monitoring. These dosimeters In the form of small pellets (6 mm diameter,

I мя thick) are made of laboratory grown CaSO.:0y (Q,\% weight) as a active TL component

and NaCl as a binder a ratio of 1:2-

In order to obtain TL single crystals of CaSO.:Dy of optical quality for dosÍmetric and

physical studies a new preparation method was developed. Single crystals with dimensions

of 5.5 x 3.5 x 1,0 mm were obtained and analysed by X-ray diffraction method (Laue), that

confirmed the monocrystal1inïty of the samples.

Detailed studies on the dos I metric characteristics such as reproducibiIityF response

linearity, fading, reusability, effect of ambient light and energy dependence were carried

out. A filter combination providing an energy independent response from 20 keV to 1,25 MeV

was obtained.

Field trials of this dosimeter and Intercompartson data have shown very good results.

5. NAME AND MAILING ADDRESS OP ORGANIZATION DOING THE WOHK

Ins t i tu to de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal f1049 - PinheirosSão Paulo - Brazi l

7. ASSOCIÍ


CNEN

9.

FROM: 0 1 / 80то J2/.83


Personal Monitoring

Assessment of Dose.DosÎmetг

TL Dosimeter

Crystal Growth

. 1 1 - Я6Р6Й6МС68 OP RECENT PUBLICATIONS IN SAME F1ËLO ISSUED FROM THIS LABORATORY

1- L.L.Campos, S.P.Kathurla, A.M.P.L.Gordon, Proc. 32a.Reunlao Anual SBPCRio de Janeiro - July 6-12 (1980) 231

2- S.P.K»thurIa, A.H.P.L.Gordon, L.L.Campos In f . - IPEN n? 93- S.B.Kathurla, L.L.Campos, A.M.P.L.Gordon Pubi. IPEN n? 32

_*" L.L.CdmpQs, J , Luminescence (1983) to be published

BRAZIL IAEA/HPRA/No.111. TITULO Y SURTITULO DEL PROGRAMA

A POSTAL KIT TO ESTIMATE PATIENT EXPOSURE FROK

MASS PHOTOFLUOROCRAPHIC SURVEVS

2. ТЕМА GENERAL

3. AUTOHISO INVESTIGADORES

Mota, H.С, Araújo, A.M., Feital, J.C.S. and Farias, J.T.

A. RfcSUMtN

In Brazil, photofluorographic x-ray machines are used for mass

tuberculosis screening. The exact number 'of t h i s equipament is

unknown, but 5000 units i s a rough es t imate . Each machine

performs about 600 examinations per month giving at l eas t 36

mill ion miniature chest per year.

The population dose from t h i s mass screening can be estimated

by a postal program.

A postal Kit i s being developed to evaluate KVp, HVL, Field

Size and Entrance Dose. This consis ts of a card whlth copper

f i l t e r s , TL dosimeters (for HVL, KVp and Exposure) and x-ray

films (for Field Size) . Monte carlo ca lcula t ion can be used

to calcula te organ doses using the Kit data as input.

INSTITUTO DE RADIOPROTEÇÃO E DOStŒTRIA - IRDAv. das Américas , Km 11,5 - Cx Postal 37025CEP: 22.602 - Rio de Janeiro - Brasil

N U ORGANIZAClONES ASOClADAS

flGANlZAClON Li OHGANI7ACIONES PATflOCIMADORAS

COMISSÃO NACIONAL DE ENERGIA NUCLEAR

ос:.'..ДЗ..../1аВЗ..л 1?.. Д98.1

10.PROYECTO - IMVESTIGACION LN CURSO -INFORME PARCIAL O FINAL CONDISTRInUCIOIJ LIMITARA 0 NO LIMITADA -INFORME i'FIFSEWTADO РАПА PUDLICACION

Postal Kit

Dosimeter

Photofluorooraphic

Surveys

to00


1. TITULO Y SUBTÍTULO DELPHOGRAMA

The Use of Tooth Fillings as Thermoluminescent Dosi-meters.

The possibility of using porcelain dental restorationas thermoluminescent dosimeters was investigated-

Personal Moni-toring|Assessmeof dose to Man

3. AUTOBES O INVESTIGADORES

Maurício, Cláudia L,P.; Cunha , Paulo G.; Rosa, Luiz A.R.

4. RESUMEM

It is very important to have a way to evaluate high doses in radiological acci-dents when the persons involved are not wearing personnel dosimeters- Nowadays almosteverybody has tooth fillings and these restorations are not difficult to be taken outquickly, if necessary. If those dental restorative materials have thermoluminescentproperties, they can be used as dosimeters in such accidents.

Porcelain was chosen to be investigated because it is very . -nployed as dentalrestoration, its TL history is completely destroyed when the matéria* is made, sinceit is heated, and it resists to some heating cycles at 3(№C. The samples were évaluâted in a Harshaw 2000 A+B TL reader. The irradiations were done in а °°Со source between50R and 2000R and with X-radiation in the energy range of 30 - 95KeV.

The porcelain glow curve presents three peaks about 110,170 and 24<№C. The fad

ing of the first peak (HO^C) is very high (100$ in one day at room-temperature). The

other peaks present no fading up to three days at room-temperature. The TL response is

linear in the exposure range investigated and has a maximum ener, y dependence of appro

ximately 500% about 30KeV.

Although the material is sensitive to light the results oDtaii.; show the possi

bility of using porcelain dental restorations as thermoluminescent dosimeters in acci-

dent dosinetry.

5. NOMBRI

Instituto de Radioproteçao e Dosímetria/CNEfíAv. das Americas km 11»5, Rio de Janeiro, RJ, Brasil

CEP; 22602 - CP: 37025

. ORCANI2AC1O4 и OHGANIZAClONES ASOClAOAS

8. ORGANIZAClON U ORGANIZACIONES PATROCINADORAS

...PL. . .1983

10. SITUACI

жяомвага-»INFORME PARCIAL O RINAL CONDI5TRIBUCION LIMITADA O NO LIMITADA -

6. с

Personal MonitoringAssessment of DoseAccident 'DosinietryThermoliiminescencePorcelainDental restorat ions


TITLE AND SUBTITLE

Manganese Doped Lithium Fluoride - Sintered Pellets PersonalMonitoring Dosimetry

Suarez, A.A., Rzyski, B.M,, Rodrigues, L.L.C.

4. ABSTRACT

The following radiation dosimetric characteristics of the TLD LiF:Mg, Ti sintered

pellets manufactured by ÏPEN-CNEN/SP were studied: TL sensitivity, dose vs. TL

response, photon energy dependence, reusability, fading.

Other characteristics are being evaluated.

NAME AND MAILING ADDRESS OF ORGANIZATION DO(I\

IPEN - CNEN/SPDivisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSao I'aulo, Brazil

ISORING ORGANIZATIONS)

CNEN

FROM-04/8JTO: L2/ 83

'TORS OR KEY WORDS

•jnoluminescenceonal monitoting.red pellotson energ> dependence

BRAZIL IAEA/HPRA/IMo.11 BRAZIL IAEA/HPRA/No.11

N>

TITLE AND SUBTITLE

The Development of a New Mathematical Phantom

Representing Closely the Adult Human for use in Internal

Dose Calculations

2. ВЯОДО HEADING

Personal _Monitoring. tlosinSFtryAssessment of Rose to Man(internal and external)


Facioloi, L.M. and Deus, S.F.

A method for the calculations of absorbed dose from internally distributed

radionuclides in the human body makes use of the concept of "specific absorbed

fraction" defined as the fraction of photon energy emitted from the source organ that

is absorbed by the target organ, per unit mass.

The interaction of radiation with matter occurs mainly by photoelectric effect,

Compton scattering and pair production. For each one of these processes the

absorption coefficients depend on radiation energy. Furthermore, the spatial

distribution of the scattered radiation and consequently the scattered energy inside

the scatterer will depend on the type and mass of materials and on their shapes.

Having this in mind a new mathematical model which represents closely the adult human

is being developed for use in internal dose calculations.

The specific absorbed fractions for the region which represents the head and neck of

this new model have been obtained by Monte Carlo techniques for discrete energies

ranging from 0.010 MeV to 4.0 MeV, considering the thyroid as the source organ. The

ratio of the specific absorbed fractions in the organs and regions of the head of the

model developed in this work, relative to the Snyder's model, ranged f n m 0.66 to

15.91 in the interval of photon energy above considered.

NAME AND MAILING ADDRESS^?? ORGANIZATION DOING ТмЕ WORK

IPEN-CNEN/SP

Divisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSao Paulo, Brazil

8. SPONSORING ORGANIZATION^)

FROM:Q6/82TO: 08/84

10. STATE OF ADVANCEMENTRf t f f iX - RESEARCH IN PROGRESS -

С. D E S C R l P T O R S O R (CEViPhantoms

Mockup

Struetural mode1s

Radiation doses

Internal irradiâtiDosimetry

Contamination

I I . REFERENCES OF RECENT PuaUCATfONS 14 SAME FIELD ISSUED FROM THIS LABOHATOH

Determination of Kadionuclides in urine and blood

2. BROAD HEADING

PersonalMonitoring. AssessmentDose to Man (internaland external)

3 AUTHORS OH INVESTIGATORS

B e l l i n t a n i , S . A . , Caburo, J.C.C., a n d S o n i i , С . М . Л . Л ,

4. ABSTRACT ., , -..

Methods of Analysis of nuelides (U , H, I) e F~ estable in urine e Pb astable in

blood of persons that might be contaminated by these sources of radiation were developed

at the Instituto <te Pesaulsas Energéticas e Nucleares (TPEN). The aim of the work is to

verify a possible internal contamination and a suitable control. The techniques to

determine the amount of uranium by fluorimetry, tritium by liquid scintillation,

iodine-131 by Nal(Tl) scintillation counter, Fluor by specific Ion electrode, lead by

atomic absorption spectrometry are already used routinely to monitor people working at

the Ipen and other institutions and industries. The quantitative determination of

thorium by activation analysis and plutonium by alpha spectrometry were developed in

1983 and will be put on routinely in 1984. In 1984 we will be developing methods for

the determination of cesium and strontium in biological materials.

5 NAME ANO MAILING ADDRESS OF OHGAN

IPEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 1Ш9 - PinheirosSao Paulo, Brazil

IZATION DOING THE

8 SPONSORING ORGANIZATION'S]


FROM. . / 8 1TO . . / Й4

10. STATE OF ADVANCEMENTЖЙШНХГ - RESEARCH IN PROGRESS -

6. DESCRIPTORS OR KEY WOROS

Bioassaybiological testing

Contamination RegulationsChemical Analysis

Todine-131

Pl-itonium-238Thorium-232

TritiumLeadFluorineCesiumStrontium

ыо BRAZIL IAEA/HPRA/No.11


Thulium doped lithium tetraborate-production, determination

of dosimetric properties, application

2. BROAD HEADING

Dosimetry

Rzyski, B.M.

Li,B 0 :Tm was fused and pülycrystalline powder or glass sheets were produced. The

powder was compacted in pellet form, sintered and it was determined the sintered

pellets TLD characteristics: TL sensitivity, dose vs. TL response, pholnn energy

dependence, reusability, fading etc.

Glaes sheets were used to study same optical characteristics as; optical absorption

and fluorescence - Tm valence changes by irradiation and the reversibility of

the process.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WOR

IPEN - CNEN/SPDivisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSao Paulo, Brazil


IPEN

PROGRAMME

F R O M : . . / .T O " - . . / . . йвскшйшвоаткюианххк

SUBMITTED FOR PUBLICATION

6.

Lithium tetraborate

Optical absorption

Glass

Thermoluminescence

characteristics

Fluorescence

Photon energy dependence

Sintered pel lets

11. f

1. Rzyski, B.M. and Morato, S.P. - 55-D.1.4 - Proceedings 34th Congress SBPC, Campinas,

S.P. Brazil, 1982. 2- Rzyski, B.M. and Morato, S.P. - 56-D.1.4 - Proceedings 34th

Congress SBPC, Campinas, S.P., brazil, 1982. 3. Others submitted.


TITLE AND SUBTITLE

Development of a CaSO,:Dy Dosimeter

2. BROAD HEADING

Personal

Monitoring

Dosimetry

Campos, L.L.

ABSTRACT

Polycrystalline pellets of a cold pressed mixture of CaSO,:Dy and NaCl powders was

developed and studied with the purpose of obtaining a personal thermoluminescent (TL)

dosimeter for radiation monitoring. These dosimeters in the form of small pellets

(6 mm diameter, 1 mm thick) are made of laboratory grown CaS0,:Dy (0.1% weight) as an

active TL component and NaCl as a binder a ratio of 1:2.

In order to obtain TL single crystals of CaSO^iDy of optical quality for dosimetric

and physical studies a new preparation method was developed. Single crystals with

dimensions of 5.5 x 3.5 x 1.0 mm were obtained and analysed by X-ray diffraction

method (Laue)» that confirmed the monocrystallinity of the samples.

Detailed studies on the dosimetric characteristics such as repruducibility, response

linearity, fading, reusability, effect of ambient light and energy dependence were

carried out. Л filter combination providing an energy independent response from

20 keV to 1.25 MeV was obtained.

Field trails of this dosimeter and intercomparison data have shown very good results.

5 NAME AND MAILING ADOHESS OF ORGANl2ATION DOING ' H£ WORI1PEN-CNEN/SPDivisão de Monitoração PessoalCaixa Postal 11049 - PinheirosSao Paulo, Brazil

8. SPONSOflING ORGANIZATIONS)

CNEN

9, DURATION OfPROGRAMME

FROM ОД/.80TO 1 2 / 83

] г Д О 6ИУШШЖ F | N A L REPORT инхннзяааквшшшидахшпиюошвкхиевавт

6. TESCRIPTOfiS OR KEY VVO

Personal Monitoring

Assessment of Dose

Dosimetry

TL Dosimeter

Crystal Growth

11 REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

1. L.L. Campos, S.P. Kathuria, Л.М.Р-L. Gordon, Proc. 32a. Reunião Anual SBPC Rio de

Janeiro July 6-12 (1980) 231. 2. S.P. Kathuria, A.M.P.L. Gordon» L.L. Campos Inf.-IPEN

no. 9. 'з. S'.P. Kathuria, L.L. Campos, A.M.P.L. Gordon Publ. IPEN No. 32. 4. L.L. Campos

J. Luminescence (1983) to be published.

BRAZIL IAEA/HPRA/No.11 BRAZIL IAEA/HPRA/No.11

TITLE AND SUBTITLE

Radiation Detectors and Calibration Development ofCalibration Laboratory

2 BROAD HEADING

DosÍmetry

Calibration

Caldas, L.V.E. , Las, W.C. and Jacomino^ V.F.

4. ABSTRACT

The main objective of this work is to complete the calibration laboratory,

establishing standard radiation fields for calibration of radiation monitors used in

radiological protection and therapy levels. Available are low and high activity

sources of Co and Cs, a beta secondary standard set-up ( Sr+ Y, Tl and

Pro) and a low energy X-rays unit (60 kV). Calibration services are carried out in

both radiological protection and therapy levels. To complete this calibration

laboratory, a high energy X-rays unit is needed; since many years we are trying to

get a used one by donation, without success. Presently measurements are being made

with free air chambers for X-rays, in order to determine their parameters for future

use in the calibration and national intercomparisons, together with our other

secondary ionization chambers.

1PEN - CNEN/SPDivisão de Mor-Toraçao PessoalCaixa Postal xlO^Í* - PinheirosSao Paulo, Brazil



FROM: 01/.81TO: 12/ S5

10. STATE OF ADVANCEMENTЯВО0БОГ - RESEARCH IN PROGRESS -


Calibration

Secondary Standardization

Radiation Detectors

. REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

High exposure dosimetry using tPR

2 BROAD HEADING

Dosimetry

Cordon, A.M.P.I. <md Las, W.C.

CaSO,:Dy (0.1% mol) produced in our lahoratory is being investigated as л probable

candidate for dosimetry in the range of high gamma radiation exposure (60 - 16 x

10 C/kg ur 2.3 x lO^R - 6.3 x 10 R) using the Electron Paramagnetic Resonance (EPR)

technique. The CaSO,:Dy crystals are anhydrous and X-ray diffraction showed

orthorhombic structure. The crystals were ground into powder and annealed at 600 С

for one hour. The EPR spectrum of single crystal CaSO,;Dy is reported elsewhere (1)-

Powder CaSO,:Dy between 3 mm lucite was submitted to different exposures of gamma

radiation, in the range mentioned above, and preliminary results indicated that the

amplitude of an EPR signal at g = 2.003 is linearly proportional to exposure

suggesting EPR as a possible technique for high exposure dosimetry.

5 NAME AND MAILING ADDRESS OF ORGANISAT

IPEN - CNEN/SP

Divisão de Monitoração Pessoal

Caixa Postal 11049 - Pinheiros

Sao Paulo, Brazil

8. SPONSORING OHGANI2AT1ONIS)

CNEN

FROM . /1983TO -./1986


6 DESCRIPTORS OR KEY WORDSElectron Paramagnetic-

ResonanceDosimetry

High Exposure

11 REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

(1) A.H.P.L. Gordon e W.C. Las - Estudos da linha isotrõpica de RPE em g = 2.00Í em

monocristois de CaSO,:Dy - Supl. Ciência e Cultura, 34(7), 267 (1982)

CANADA IAEA/HPRA/No.11 CANADA IAEA/HPRA/No.11

Development of Diffusion-Based RadonDaughter Dosimeters

2. ВЯОАО HEADING I

Personal MonitortineDosimetry. Assessment: ofDose to Man (internaland external)

% AUTHORS ОН INVESTIGATORS

PHILLIPS, C.R.

Passive devices for personal radon daughter estimation would offer greac advantages

in terras of size, weight and cost reductions, if adequate sensitivity and

durability could be maintained. To this end, electrostatic and thermophoretic

collection principles are being investigated in an effort to determine the

feasibility and adequacy of these principles to a practical passive radon daughter

dosimeter.

IAME ANO MAILING ADDRESS OF ORGANIZA

Dept. of Chemical Engineering & Applied ChemistryUniversity of TorontoToronto, Ontario, CanadaM5S Ш

7. ASSOCIATED O R G A N I Z A T I O N ^

8 SPONSORING ORGANIZATIONISI

Atomic Energy Control Board

ЯНОМ 7 •

TO 3 '

Research in progress

exposuredosimetryihysicsradiation protectionradionuclides

1 TITLE ANO SUB

Design of a Passive Personal Dosimeter For Mines Using AnAllyl Diglycol Carbonate Plastic

PersonalmonitoringDosimetry, Assessmentof Dose to Man (intern;and external)

PAL, H.L.

ABSTRACT

The objective of this Proposal is to design a passive personal dosimeter for uraniumminers using the CR39 detector. Based upon knowledge of the general disadvantages ofthe passive system and the experience obtained from existing designs (U.S. Bureau ofMines), a new method for a passive system is suggested which can be expected to have asensitivity of at least 0.05 WL with a precision of 30%. The new system can bedesigned Co differentiate radon and thoron working levels which is especiallyrequired in Canada. Since the passive device would depend upon the proper activesystem for absolute calibration, a hybrid system using both the active and passivedevices is suggested. Depending upon the future technical development of thepassive system and the future cost of the active system, the ratio of number ofpassive devices to that of the active devices can be decided based upon cost benefitanalysis and the special conditions of the mine.

5 NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

R.A.D. Service and Instrument Ltd.14 Alicewood Crt.Rexdale, Ontario, Canada, M9V 3Y2

7 ASSOCIATED ORGANIZATIONS

SPONSORING ORGANIZATIOI41S1


FROM 1 2 ' 8 2TO 1 0 ' 8 3

Research in progress

lESCRlPTORSQR KEY

dosimetryradiation protectionexposurephysics

CANADA IAEA/HPRA/No.11 CANADA IAEA/HPRA/No.11

Co

I. TITLE AND SUBTITLE

Dosimetry, Measurement and Properties of Radon Daughters

and Thoron Daughters

Personal Monitori ng.Dosimetry. Assessment atDose to Man ( i n t e r n a l antexternal)


PHILLIPS, C.R.

4. ABSTRACT

To compliment the development work on personal radon daughter dosimeters being under-

taken by the Department of Energy, Mines and Resources, measurements of several

physical parameters of radon and thoron daughters were performed at the University of

Toronto. These measurements included plate-out effects, alpha particle response of

TL materials, unattached fractions and charged fractions in diesel and non-diesel

mines.

5. NAME AND MAILING ADDRESS ОЯ ORGANIZATION DOING THÉ WORK

Dept. of Chem. Engineering & Applied Chemistry

University of Toronto, Wallberg Building,

200 College St., Toronto, Ontario, Canada

7 ASSOCIATED ORGANIZATION^)

6 SPONSORING OROANIZATION(S)



FROM: .5/.90TO: .1/.82


Partial or ítnal report with

limited or unlimited distribution

Report submitted for publication

6 DESCI

dosimetry

exposure

biology

physics

uptake

radiation protection

Further Development of Personal Radon Daughter (and ThoronDaughter) Dosimeters Using TL and Track-etch DetectingMaterial

2 BROAD HEADINt

Personal Monitorii g.

Dosimetry. Assessment ofDose to Man(internal andexternal)

BIGU, J.

4. ABSTRACT

The Atomic Energy Control Board has enlisted the Canada Centre for Mineral and Energy

Technology (CANMET) to improve the performance of radon daughter (and thoron daughter)

dosimeters that utilize thermoluminescent (TL) and track-etch detecting materials.

Extensive measurements have been made on these dosimeter types in mine environments,

and laboratory facilities are being equipped with a view to providing information on

the limitations of the dosimeters and, ultimately, to effecting improvements in

them.

CANMET, Department of Energy, Mines and Resources

Elliot Lake LaboratoryP.O. Box 100, Elliot Lake, Ontario, Canada P5A 2J6

7 Associated Crganization(s)


Department of Energy, Mines & ResourcesAtomic Energy Control Board


FROM- A / 79TO- .3 / .82

10. STATE OF ADVANCE"

PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION

6. DESCRIPTORS OR KEV И1ОЯ

exposure

dasimetry

physics

mines


CANADA IAEA/HPRA/No.11

Î. TITLE AND SUBTITLE

Testing and Evaluation of Existing Analysis Techniques forIdentifying Uptakes and Measuring Retention of Uranium inMill Workers

2. BROAD HEADINI

Personal MonitoriDosimetry. AssessDose to Man (internaland external)

3, AUTHORS OR INVESTIGATORS

D A V I S , M . W . ; GERDINGH, R . F . ; ELLA, J .

4. ABSTRACT

The extent of lung contamination of uranium among mill workers in Canada is not

precisely known. The retention of uranium directly influences the radiological dose

received by the workers. This study tests existing analysis techniques for

identifying uptakes and measuring retention of uranium in mill workers.

Evaluations of bioasaay determinations of uranium in urine and lung, and a radiation

monitoring program that includes air sampling in the mill, tests for solubility

In simulated lung fluid, and tests for the Th234/U238 equilibrium factor, are

presented.

Monserco Ltd.6620 Kitiroat RoadMississauga, OntarioCanada L5N 2B8


McMaster University

8. SPONSORING ORGANIZATIONS

Atomic Energy Control BoardDepartment of National Health and Welfare

9. OURATION OFPROGRAMME

FROM: >. /.82TO: XZl 82

PROJECT - REPORT SUBMITTED FORPUBLICATION

6. DESCRIPTORS OR KEY WOP

exposuredosimetrybioassayuptakemillsradiation protection


Determination of the Feasibility of Using Bioassay andIn-Vivo Measurements in Uranium Workers for Dose Calculations

2 BROAD HEADING

Personal Monitoring.'Dosimetry. Assessment ofDose to Man (internal and


AVADHANULA, R.

4. ABSTRACT

The most accurate means of determining the amount of uranium in the lungs is that oflung counting. In Canada, this is an expensive and time consuming process due to therelative locations of the uranium work sites and counting equipment.

This study investigates the suitability of frequent urinalysis combined with airmonitoring of the uranium workers* environment as an accurate, rapid and inexpensivemeans for the estimation of natural uranium in the lungs of fuel fabrication workers.

Data on spot and 24-hour composite urine samples, daily personal air samples and lungburdens were collected from personnel working for two Canadian nuclear fuelfabrication companies.

Regression equations were derived to estimate the daily uranium excretion based onspot urine sample analysis and daily creatinine measurement. Creatinine-basedestimates of daily uranium excretion, using (simple) logarithmic regression equations,were found more reliable than volume-based estimates. The standard errors of estimate,coefficients of variation are also presented. The importance of collection time of spoturine sample is discussed.

5.R. Avadhanula and Radiation Protection BureauDept. of National Health and WelfareBrookfield Road, Ottawa, OntarioCanada K1A ICI


Atomic hnergy Control BoardP.O. Box 1048Ottawa, Ontario, Canada KIP 5S9

8 SPONSORING ORGANIZATIONS!Atomic Energy Control BoardDepartment of National Health and Welfare

FROM-6 79TO 12 / f i l

PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION

dosimetrybioassay

biologyuptakefabricationexposureradiation orotectionmodelling

CANADA IAEA/HPRA/No.11 FINLAND IAEA/HPRA/No.11

1 TITLE A N D SUBTITLE

Determination of the Contribution of Respir.ibU- LonR-Lived

Dust to Lung Exposure in the Uranium Industry

2. BROAD HEADING

Personal Monitor-

ing. Dos Lmutry. Assessment

of Do sir to Man (internal

anJ exL..*-riaI)

DUl'ORT, P.J.

4. ABSTRACT

Long-lived radioactive dusts such as uranium, tiiorium and radium contribute an

as yet, unquantifled fraction of the total lung dose to workers in the uranium

industry. Measurements of the concentrations, sizes, distributions, respirable

fraction and other relevant parameters related to these dusts are being made in

uranium mines and mills. These quantitative determinations will be used to

estimate, using appropriate lung models and other biological parameters, the

contribution to the human respiratory system that may arise from Che inhalation <

such dusts.

Canadian Institute for Radiation Safety

P.O. Box 460, Elliot Lake, Ontario

Canada

P5A 2J9

6. SPONSORING ОЯОД1\пгдТ1О1М<51


9. DUHATÍOM OF

PROGRAMME

FROM. \ I ?.2

TO $./?.4

10PROJECT - RESEARCH IN PROGRESS -

6. DESCRIPTORS OR K E * WORDS

exposuredosimetryaerosolsuptake

radiation protectionmodelling

Personal Monitoring in the Nuclear Medicine Depart- Pcrsonal Moni-toring


Porkka Leena, Suutala Merja, Kairento Anna-Liisa, Tanmnen Arja

We have performed personal monitoring of absorbed doses in differentparts of the body on personnel of the nuclear medicine departmentworking on three different areas. The groups are (1) medical physicians,who inject activity and examine patients/ (2) technicians, who are carry-ing out medical imaging using gairanacameras and (3) those technicians,who are working with radioimmunoanalysis. The doses are measured withCaSO.:Dy powder dosemeters, which are calibrated with ymTc (140 keV)against the calibrated ionisation chamber. ^ c is the mostly used radio-active isotope in our department (about 3700 GBq/year).The results show that the left side of the chest is an optimal place tocarry a dosemeter for monitoring whole body doses. Average_absorbedwhole body doses in different groups were (1) group (4.41 + 2.34)mSv/year, (2) group (3.41 + 3.07) mSv/year and (3) group (0.23 + 0.20)mSv/year. Hand doses were (7.77 + 4.02) mSv/year, (4.99 + 3.10) mSv/yearand (0.36 + 0.20) mSv/year respectively.

DORESS OF ORGANIZATION DOING THE W

Helsinki University Central HospitalDepartment of Clinical ChemistryDivision of Nuclear MedicineHaartmaninkatu 4 SF-00290 Helsinki 29


Institute of Radiation Protection

В SPONSORING OH

FROM 1'83TO / -

-personal monitoring-CaSO.:Dy TLD-dosemete'-absorbed doses

I

FINLAND IAEA/HPRA/No.11 FINLAND IAEA/HPRA/No.11

LE AND SUBTITLE

Correlation between absorbed doses exposed to staffand used radioactive isotopes

Personal monitoring


Kairento Anna-Liisa, Porkka Leena

We have studied correlation of absorbed doses exposed to the staff dueto used radioactive isotopes in diagnostics in the nuclear medicine de-partment. In the,last few years the mostly used radioactive isotopes havebeen 3 3 mTc and XI. The number of examinations with " " V c during theyears 1977-1982 raised from 1950 to 2424 and the total injected activityfrom 529 GBq to 1290 GBq, respectively .The used I activity was duringthis time (4.20-0.41)GBq/year. The range of the individual whole bodydoses to the medical physicians was (0.5-2.73)mSv/year and to the techni-cians {0.5-2.61)mSv/year. The cumulative doses to the above groups was(3.3-8.5)mSv/year and (3.1-18.3)mSv/year, respectively. The whole bodydoses to the whole staff varied ranJomly.The monitoring was carried outwith film badges and registrati<-:, limit was 0.5mSv/year. We did not findany correlation between absorbed doses and used activities.Cumulative hand doses exposed to the staff increased from 16.6mSv/yearto 85'. 6mSv/year over the same period and it had significant linear corre-lation to the used activities,p<0.1, corresponding correlation concerningonly the qroup of technicians was 0.964 and p<).001.

t€SS OF O«GAf4f2ATiO« OOfNG THE WORK

Helsinki University Central HospitalDepartment of Clinical ChemistryDivision of Nuclear MedicineHaartmaninkatu 4, SF-00290 Helsinki 29

5PONSOHING ORGANIZATIONS!


FROM' l $ 3TO .. ' .

p4flffiKR- RESEARCH IN PROGRESS -

S ОН К Е * WORDS

-absorbed doses

-personnel monitoring

Options to facilitate TLD in practice

2 BROAD HLAD1NG

Dosimetry

Matti Toivonen

Some special options were developed for a TLD system. TL detectorscan be automatically irradiated in the TLD reader with a 90sr source.The automatic irradiation is used to determine the individual sensitivitycorrection factors of TL detectors. These are stored in a magnetictape on the dosemeter card. For therapy dosimetry the reader is providedwith a program in which the measuring results are first stored on adiscette and in the second step corrected for the differences in theindividual sensit ivit ies of the detectors. The correction is madeby irradiating and reading the detectors afterwards. The applicabilityof the system to personnel monitoring, to therapy dosimetry, to radondosimetry and to special purposes like neutron dosimetry will be studied.

5. NAME AND MAILING ADDRESS OP ORGANIZATION DOING THE WC


P О Box 268, SF - 00101 HELSINKI 10

FINLAND

ASSOCIATED ORi

8 SPONSORING ORGAN.2

FROM 8 ''82TO \2'B3

PROJECT RESEARCH IN PROGRESS -PARTIAL OH-FWAfc-ОСРОПТ WITH LlMt?0П UNLIMITED DIGTniDUTlON - REPORSUBMITTED FOR PUBLICATION

. DESCRIPTORS OR KEV WORDS

TLD system

Automatic TLD

LToivoncn, M.J.i Individual TL detector characteristics in automatedorocessing of personnel dosemeters : Correction factors as extensionto identity codes of dosemeter cards. Report STL-A27, Helsinki 1979, 19 p

2. Bjarland, в., Toivonon, M., Microcomputer controlled automatic TLD reade.Trans. IZEE NS-27, No. 2, 969-973 (198Q). .

FRANCE IAEA/HPRA/No.11

UN NOUVEAU TYPE DE DETECTEUR PORTATIFPOUR LA DOSIMETRIE DES NEUTRONS AU NIVEAU

DE L 'AMBIANCEDOSIMETRIE

M. MOURGUES

* " " T e DINEUIIÎON est un nouveau type de détecteur d'ambiance destiné àla dosimétrie des neutrons. Il est né de l'analyse des chumps derevonnement neutronique propre aux installations industrielles. Cetteanalyse a montrii qu'il était possible de concevoir, pour cet usage, undispositif ò la fois plus léger et plus sensible que les rem-mi-treshebi tuels. . L ,, , .

Le capteur du DINEUTRON est constitué par un compteur à hi.lium-Э dede petites dimensions placé au centre d'un sphî-re de polyé thy lène de 10cm de diamMre. La réponse en énergie est sensiblement proportionnellea la fluence des neutrons entre 1 eV et 500 keV et donne le maximum desensibilité dans cette gamme d'énergie (en moyenne 0,35 impul-sions/n.cm-2, ce qui équivaut à 35 impulsions.s-l/mrem.h-1 pour laréponse en équivalent de dose), valeur très supérieure à celle desdispositifs habituels. La réponse en dose n'étant pas indépendante del'énergie, un dispositif d'autoétalonnage a été mis au point, ce quipermet l'utilisation du DINEUTRON depuis les neutrons thermiquesjusqu'à UMeV. Des fonctions de transfert jointes a ui calculateurdonnent acc&s aux mesures suivante: l'équivalent de dose, la doseabsorbée, le facteur de qualité, on débit et en intégration pour lesdeux systèmes d'unit'éa actuellement en usage.

CE.A. CEN/CADDPT/SIDR/LDNCADARACHE O.P. n° 113115 St Paul-lez-Durence

CE.A.

01/8112/83

ТО. СТАТ 04

I32SESK- F

DOSIMETRIE DESNEUTRONS

COMPTEURS AHE-3

IRRADIATION EXTERNE

Utilisation" de' chambres a fission de grande sensibilité pour1) .Л-a'.Sfyestr-nmiilr-ie.. e-b-la-DanimS.tr le. .des neutrons. M. MOURGUES.

2i AIEA-SM-229/84 VIENNE, 1979-


ETUDE ET REALISATION DE

D05IHETRES INDIVIDUELS DE NEUTRONS DOSIMETRIE

M. BUXEROLLE

Le D1N est constitué par un boîtier en aluminium enveloppé d'unfiltre de cadmium dons lequel est glissé une tirette également enaluminium comportant 4 elvéolesf des frittes thermoluminescent s (PTL)sont disposés dans ces alvéoles:

2 PTL 717 en fluoré de lithium enrichi en lithium-7, sensiblesaux rayonnement gamma mais très peu sensibles aux neutrons.

2 PTL 716 en fluoré de lithium enrichi en lithium-6 (99ÜLÍ-6)sensibles au rayonnement gamma et trfcs sensibles aux neutrons de basseénergie -

Le principe du DIN est le suivant: les neutrons incidents sontralentis et diffusés par le corps du porteur du dosimètre (albédo) etdonnent, ainsi que les neutrons directs de basse énergie une réaction(n,ot) avec le lithium-6. Les frittes thermoluminescents étant aenaiblesau rayonnement gamma, le signal dû aux neutrons est obtenu .pardifférence entre les lectures Li-6 et Li-7 enregistrées respectivementsur les PTL 716 et 717.

L'épaisseur du filtre de cadmium a été choisie de manière à ce que lasensibilité aux neutrons épithermiques soit égale è la sensibilité auxneutrons thermiques. Depuis le début de 1982, le DIN est utilisé enroutine dans les ateliers de technologie du plutonium, du CEA è

CE.A. CEN/CADBPT/5IDH/LDNCADARACHE O.P. n° 113115 5t Poul-lez-Durance

С.С.Е./С.Е.Д.

1/198112/1984

СНЕПС^5 г.ч courts -

D0S1METRES ANEUTRONS D'ALBEDO

FLUORES DE L I T H I U M

D O S I M E T R I E DUPERSONNEL

1) Jntlu&ncc. .. .of.. .1 igh.t-.. tra-nsmis-sion on the response of .LiF„•thermoluminescence d e t e c t o r s to thermal n e u t r o n s . M.Suxerolle,'T'.SpVirhV'.'ftàWioprofêctïdii'bosiméVry';' У о Г З , № 4. 1982 pp 233-235.э*

* selan le =as


1. TITAI (T*QUS-1lTfl«

OETECTEURS Л TRACESDOSIhETRIE

R. MEDIONI f F. BERMANN

Pour résoudre les problèmes posés par le dosimètrie individuelledee neutrons dans les laboratoires du CEA nous nous sommes orientésvers deux techniques:

-Le thermoluminescence: deux détecteurs 6LiF et 7Li Fcontenus dana un boitier recouvert de cadmium permet la detect ion

des neutrons d'énergie faible (albedo).-Les détecteurs solides de traces: un détecteur de ni trate de

cellulose recouvert d'une couche de tetraborate de lithium ( con-vertisseur (n,cc) ) est utilisé. Ce détecteur est commercialisé par KodakPathé France.

Les deux techniques impliquent une calibration aux différentspostes de travail (évaluation du coefficient dose/signal enregistré).Les doses de références sont déterminées par le système multisphère(déterminaton du spectre et calcul de l'équivalent de dose)

Les résultats montrent que la valeur du coefficievarie d'un facteur 1 a 5 dans un même laboratoire;du temps passé & chaque poste de travail est doncl'avenir un détecteur multielement sera étudié. Il dedé tecter les neutrons dans di fférentes bandes d'uniainsi les variations du facteur d'étalonnage des dé te

t de calibrationa prise en comptenécessaire. Dansraifc permettre dergie et réduireteurs à traces.

Г ^ . А . CEN / FARDPT / SIDR BP n

n6

92260 F0NTENAY-AUX-R05ES

t, «OUftCllil OC f\n,C*ÊC.T.7EURATOM

1979

10. СТАТ ОЧ

DETECTEURS PAR" TRACESDANS DIELECTRIQUE

FLUORES DE LITHIUM

ETALONNAGE

DOSIMETRIE DESNEUTRONS

l î ..S1S,.NM,P.%.ceXibrB.t.i.on i n . . .4 . . P.e.4tr°n source f a b r i c a t i o n hotl a b o r a t o r y . R.MEDIONI, F.BERMANN, 3.M.B0RDV, G.PORTAL. CombinedOOE'-riéùfro'n'w'oYI<shop'/EUR7UOM-1CeíVDO-S 'conference.

FRANCE IAEA/HPRA/No.11t . TIT

DOSIHETRIE INDIVIDUELLE DES RAYONNEHENTS BETADE FAIBLES ENERGIES PAR EMISSION EXOELECTRONIQbT

THERHOSTIMULEE (EETS)

RADI0PR0TECTI0NI

M.PETEL, J.BARTHE, G.PORTAL

fltSUWE

Notre Laboratoire s'est depuis une dizaine d'années spécialisé dansla détection des émissions exoôlectraniques thermo et photo-stimu-lées ( EET5,EEPS ) . Les dosimètres a émissions exoâlectroniquepeu vent être conçus "équivalents tissus" en utilisant un supportadéquat - L'épaisseur de leur couche sensible, très mince, estcomprise entre 1 et 10 nanometres.

Nous avons sélectionné deux matériaux exoémetteurs très sensiblesqui peuvent apporter une solution à la détection des rayonnementsbêta de faibles énergies. Il s'agit du fluorure de lithium et de1'oxyde de beryllium.

La détection des exoélectrons est effectuée au moyen d'un lecteurd'EETS développé dans notre Laboratoire et commercialisé par laSociété D1GITEC ( FRANCE ).

Nous avons également const ruit un appareillage de lecture automa-tique en vue d1effectuer des mesures de routine plus rapides.Il estéquipé d'un système de transfert des dosimètres sur un four de pré-chauffage qui élimine les pics du thermogramme inutilisables endosimètrie. Les dosimètres sont ensuite transférés sur un deuxièmefour sur lequel est disposé la tête de lecture ( compteur ) quieffectue la mesure.

CE.A. CEN/FARDPT/SIDR BP nD692260 FÛNTENAY-AUX-RDSES

Physikalisches Institut.Heinrich-Buff-Ring 16.D-630Q

Giessen

С E A / EURATOM

DOSIMETRESA EXOELECTRONS

FLUORES DELITHIUIM

OXYDES DEBERYLLIUM

M u l t i n e e d l e c o u n t e r w i t h cathode f o c u s i n g (MPCF) used f o r*' c f o e l m V f r y ^ e É ê V e T ê y i n t ^ C b n f .'StVasbourg FRANCE March 1982.-. Dosimè-Ьрев- • -basées • sur • 1 * é-miss-i-on • • e-*oé lectronique thermostimulée

(EETS) du L iF . B.ïatah, Y.Herbault, M.Petel, G.Portai .' " "findi nníniWrt inn "VpV H ' n°4 ' 19ÍÍZ;

selsn le cas


REALISATION ET CARACTERISATION ПК SPECTRKS DE

FISSION DEGRADES

DOSIMETRIE

RADIOPROTCCTIÜN

J.L.CHARTIER - M.CERUTT1

La réal isat ion et la mise au point des systèmes dasunétriques u t i l i s é s dans les mesuresdes neutrons en radioprotection necessite de disposer des iroyens d'étalonnage appro-priés, c ' e s t â dire des champs de rayonnement neutronique réa l i s tes , caractérisés entermes de distr ibution en énergie e t dans les grandeurs dosimétriques appropriées.

Les travaux actuels sur la réalisation de spocuroa dégradés â pa r t i r de la fissionprovoquée par les neutrons de 14 MeV d'un accélérateur SAMES 150 kv (d-T) concernentla mise au point du système monitoraqe par "particule associée" et l'étalonnage enfluence e t en kerma du faisceau de neutrons de 14 MeV. Par a i l l eurs , une premièreétape de la caractêrisation du spectre issu de la sphère d'uranium 238 entourant lacible emissive consiste en une sùnulation par calcul Mante-Carlo des specLre y etneutrons aux points d'étalonnage d'instruments, tenant compte de l'environnement del ' ins ta l la t ion . Ces calculs sont complétés par ceux concernant l ' influence d'écransdestinés à modifier la distr ibution énergétique aussi obtenue pour approcher les spectreréels rencontrés auprès des instal la t ions nucléaires.

C E . A . CENPAR

DPT/SIDR B.P.N°6

92260 FONTENAY-AUX-ROSES

C E . Д . / EURATOM

-19.83.

- 4984-

NORMES

SPECTRES DESNEUTRONS


II. .

DEVELOPPEMENT D'UN MATERIAU TMERMOLUMINESCENT

POUR LA DOSIMCTRIE OES RADIATIONS IONISANTES

(LE RORATE DE LITHIUM ACTIVE AU CUIVRE)

DOSIMETRKRADIOPROTECTION

G.MARINELLO, R.V1S05EKAS, S.LORRAIN

*• *E5wtfbtre objectif est de disposer rapidement d'un dosimètre thermo-

luminescent, dont les qualités repondent aux exigences les plus sévèresdu domaine médical ou de la Radioprotection.

On achevé la mise au point de sa préparation selon une varianted'une méthode connue en recherchant a la fois une optimalisation duproduit et une technologie capable d'en fabriquer en quantité relative-ment importante. On étudie les principa'les propriétés physiques: seuilde détection, sensibilité aux diverses radiations selon leur nature etleur énergie, courbe de réponse en fonction de la dose (domaine delinéarité, supralinéerité), stabilité de l'information stockée enfonction du temps et de la température de conservation "fading" et1'hygroscopicité. Pour chacune des applications envisagé

;з, on

recherche la forme physique la mieux adaptée (pellicule, poudre,fritte). Le programme des travaux comprend:

- une extrapolation de l'échelle de production du borate de lithiumdopé au cuivre de formule optimale, avec contrôle et suivi descaractéristiques physiques.

- la recherche du meilleur conditionnement et d'une procédure demesure visent a améliorer la situation présente dans les applicationsenvisagées du domaine clinique ou de la Radioprotection.

CE.A. CEN/FARDPT/SIDR O.P. № 692260 F0NTENAV-AUX-R05ES

q Henri Hnndor

-Université Pierre et Marie Curie. Laboratoirede Luminescence

D.G.R.S.T.

11/19B26/1984

COMPOSES DE L I T H I U M

BORATES

1 ) . .

г) ..

• selon le cas

INDIA IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11

mmpirioal Fitting of Radiation Detector Responses using aQuasi Random Search Algorithm

Basdyopadhyay T. and Загкаг Р.Г..

. ABSTRACT

In order to determine the induced sotivity or the response fonction of *radiation detector, the count distribution i u to be fitted with the response funationof the drteotor. The problem reduaes to that of non linear optimisation in order toestimât» the parameters that giras the beat f i t . The methods commonly used are thegradient search technique anil the linear Taylor differential correction technique* Thefoner eannot be used i f gradient i s discontinuous and the latter h u the problem ofmatrix inversion.

1 quasi random search technique has been developed to avoid these shortcomings. 1random search for the minima ia osrried out over the entire function space and thisresulta in a simple algorithm. The hyperãisensloual space is scanned to get a reliableoonverjenoe by usine a quasi random sequence. The Halton sequence having minimaldispersion ia uaed in the present work.

The performance of the algorithm i s tested with computer generated data and withmeasured data using a Kal detector. Comparisons with gradient search technique andTaylor differential correction technique show that the present method gives betterresults especially for data with poor s tat i s t ics .

NAME AND VAILING ADDRESS OF ORGANIZATION DOING T

Health Fhyeiea Volt,VÍC Centre,Ï/U, Bldhan ««gar,Calcutta 700 064.

7. ASSOCIA

8. SPONSORING ORGANIZATIONS!

Shabha Atomic Research Centre


FROM:. . / 19S2то. ../.1983

РПО1ССТ - RESEARCH IN PROGRESS -PAflflAt-en-fWAUlEPORTÏUIH UMiTEOOR-UNUMITED-DISIRIBUTIOU - HEPBRTSUPMITTCD rOHWBUCATION

Detector ResponseUnfolding

1 1 . REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABOHATOR

In-vivo uranium Detection with a Shadow-ehield Bed Countei

S.F., Sharma B.C., Baridaean Т.К. and Surendran T.

4 . ABSTRACT

The capabilities of a sbadow-ehield counter for the measurement of lung burdens ofnatural and enriched uranium by detecting gaama-radlatlons (60-90 ke? fro» 234Th and2 3 1Th and 185 Tail from 235n) externally, were inveatigated. Two types of detectionsystems were employed - 12.7 cm x 1.27 cm. Hal(Tl) and a 20 ca. dia phoawlch 3 mmVal(Tl) 5 cm CiI(Tl) operating with pulse-shape discrimination technique. The shsdorshield optiaised for 15 cm thick steel was further provided with a graded Z lining of3 i i m P b + 2 » » C d * 0.5 ma Cu.

The calibration of the two detection eyateas was carried out with a HBMCALphantom containing saw dust and Vat. U sources in i t s lungs. The minimum detectableact iv i t ies obtained were 3.3 and 5.4 mg for the phoswich and Val(Tl) detentor

regions were 3.0 and 13.0 mg respectively.

A shadow-ehield bed counter based on this has been installed at Unclear FuelComplex, Hyderabad, for routine monitoring of personnel handling Hat./enriched №The evaluation of the system in plant environment i s currently In progress.

Uranium.

LING ADORESS OF ORGANIZATION с

Health Fhysics Division,Bhabba Atonic ResearchBombay 400 085

ASSOCIATED OHGANlZAT(ONIS>


Shabha Atonic Research Centre

10.

FROMTO

'1976. /Continuing

PHOJECT - RESEARCH IN PROGRESS -PAfTTtAL Ofí-FINAL BEPORT WJT) I btMfTEDORUNL1MITCO EHSTWBÜTtON—REPORT5МИМ1ТТГП CATPN

tjraniun. Lung Counter

a. Kapur D.K. et al Journal of Mysore Uairerfcity 26 (1976) 277.

b. Garg 3.P. and S her» a R*C, Health Physics (Subnitted)


1 TITLE ANO SUBTITLE

Syittelo fie Burden In Uranlta Miner* By MettsurMent ofEadoa ifi Exhaled Breath

2. BROAD HEADING

Personnel Monitories


3riYaatara G.Ï., Ragharayya X., Xotrappa P. and Soaasundirea S.

Breath radon aessureaent ia uaed aa an eetiaata of radiua-226 body burden. Astaple and portable ayatea haa been derelopeil for routine aeasureaent of radon inbreath and radiua body burden of oooupational workera. Uraniua ainera «ere aaked toinhale radon-free aedioal oxygen and exhale throu^i a 5.2 litre aluainiim chsaberbefore proceeding for work, the chaaber waa aealed and iaolated froa the saaplingoirouit. in eleotrostatio plate colleoted the freahly foraed radon decay producta.The subsequent programed alpha counting of the plate yielded radoK concentration i sexhaled breath, laauaing that the exhaled breath represents 70)6 cr radon produced inthe body due to ayataaio burden of 22бВа, the ЪоЗт burden ia calculated. Standardi-aation of proeadurea and the data collected on 181 «inert are ditoaaaed.

The prooedurs ia siaple and adoptable for routine aeaaureasnta aince the ainerneeda to be in the laboratory only for 10 aine. The ayatea i s also portable for fieldapplication, for routine use, the detection l ia it la 0.15 kBq, which ia well below10* of the body burden l iait of 3.7 kBq for г г 6 Еа.

G ADDRESS OF ORGANIZATION DOING THE WORK

Health Phyalcs Obit,П.С.1.1., Jaduguda.Slnghbhia, Bihar.


Bhabha itoaio "eaearoh Centre


FROM: ../.1.981

TO: . . / .'1984

10. STA

ПС5ЕДПС» IN HnOCRCSS -

riWAL RFPORTWITH LIMITCDОП UHUMITGD PIOTniBUTION - REPORTSUBMITTED FOR PUBLICATION

6. DESC

áadluaCranlue VineBody Burden


TITLE ANO SUBTITLE

Sffectite loss equiTalanta fer Beutren Spectra.

Dtae equlTaleni


G. Tenkataraaan, V-S. Uhairyawi

Iffeetlve aeae aqulvalenta per unit nsutren fluenea far brea< range ef flsalesnautran speotra leakii« threugh rarlaua ahieUa ax« far neutrena free laberateryneutreo seurces Ьата been ealoulata* fraa publlahe* depth «ess flstrlbntlensfer these nentren apeetra.


Mrlslon of Badialegioal Preteetiea,Bhabha Atealo Baaeareh CentraTreabay, Beabay-400 065, In41-<.



FROM. JUKI 1982то. для 1983

10 STATE OF ADVANCEM6NT

PABTtAL OR FINAL REPORTWITH fc

Oft UNLIMITED DISTRIBUTION - REPORT

Iffeetli» leasequiTalents,Beutren spestra

1. И.Р. Ihairyawan, Bffectiw Bess equiTalents far Seas of the Beutren Ssoroes 4se*in Industry and Researeh, Bulletin ef Baaiatien Pretaotlen, Vel 6, le.1, 198Î,pb 2? . W- (2 ) . *.P. Uhairyawan anl G. Tenkatara^, Sffaoti» Baaa equiralents

fer Iaakma Meutron sMatra, Radlatlen Preteatlan pealaatry, Tel.4, Me.2,1983,PP 105-107'


1. TITLE ANDSUBTlTLE

"Phetsn tosrty Impendence »f Varisue Я, peaks 1лL1Ï (TUVIOO)

2 BROAD HEADING

Doslastxy

lhuwm Chandra, A.It. Lakshaanan and И.О. lhatt

ABSTRACT

Photon energy dependence of TL peaks 4,5.6 and 7 In Tirgin and 145*C-24npre-trHtei LIP (TLD.100) was stndled in tha range 29-1250 ]nV. It was obientd thatonly peak 7 ation higher energy dependence м eoanared to other TL peaks. Thislndloetss that paak 7 corresponds to 2-hit trapa. Лак 6 intensity which gataenhanced by a factor of about 4.5 after 145*C-24h pre-treataent ahom energy dependen-o* doa* to that of peak 5. Although th« effect of 145*C-24h pre-treataent on theIntensity of paak 7 la negligible, peak 5 geta reduced by about a factor of 45.

BlTialon of Badlologlcal ProtectionBbabha Atoale Beaearob Centra,fiRMbay, Bo»bay-400 08;India.


Stpartaent of Atoaic №ergy, India.

repartent of Atonic Energy, India.

FROM: /.Jan. 82TO: ..I ГеЪ. 82


PROJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6- DESCRIPTORS OH KEY WORDS

LIP (TLD-100)

REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM T H I S ^ABOFlATORY

Mrawan Chandra, A.R. Ukehunan and B.c. Bhatt, Int. J. Appl. Bad l i t . Isot. Toi. 33,pp.1599 to 1402, 1982.

"tapenàenct of tberBolualiwseenoe sensitivity ont«rarperatui« of Irradiation in Liï (TLD-100) phoaphar

2 BROAD HEADING

Doalaatry

Miunn Chandra, A.R. Lakahnanan and B.C. Bhatt

A atrong dependence of the intensity of the theraoltmineacenca (TL) outputof peaks'(208'C), 7(266'C) and Ю(422'С) on temperatura (Tj^JCin tha rang* 25-295*C)at which the phosphor sa«plea u n irradiated « u observed In LiF(TLD-IOO) In the doaerange corsred by us (1.7 x 102-2.5 x WGy). Below the dosa lerel of 1.26 x 10'0y, theintensity of peak 10 n e 35-75)' higher for high T rj. coapared «lth the rocav-teqperature(25*c) irradiation. Aboie 1.26 1 lO'Gy, a rereraal ««« obaerred in «hlch the deereaentin TL intensity of peak 10 Increased with Tjrr. In general, the TL Intensities ofpeaks 5 snd 7 deoreas* with increasing *lrr- Я» senaitlsation of pealt 7 depends entha Intensity of peak 10. The sensltlsatlon of peak 3 at high T l r T i s ноте than thatat 25*0 for pn-dosea below 1 .2É x ЮЗСу and a revere» 1 ia thin observed froa thisdoae onwards. We explain ltcreaee of TL intensity and S/So at high teaperetaree u

due to increaaed elimination of ccarpetltors to luaimacent oentrea.

LINC AOORESS OF ORGANIZA

Division of Radiological ProtectionBhabha Atonic ieiaearoh Centre,Trombay, Bombay, 400 085, India

ASSOCIATED ORGAMZATiONlSl

Department of Atonic Bnergy, India,

SPONSORING ORGANIZATION (Si

Department o f A t o a l e Energy, I n d i a .

FROM.TO

Hay 81July 81

10 STATE OF ADVANCEMENT

PROJECT RESEARCH IN PROGRESS-PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6 DESCRIPTORS OR * '

LIP (TLD-100)

Bhuwan Chandra, A.H. Lakshnanan and Я.С. Bhatt, J. Fhya. D. Appl.18*6-1816.

e., 15(1982)


I TITLE ANO SUBTITLE

"Doiisetric Characteristics of Thsraolualmsomt LiF(Mi, Cu,P) phosphor"

2. BROAD HEADING

Bo alee try

3. AUTHORS OR INVESTIGATORS Rruwan Chandra, 4.S. Pradhan, A.R. Lalcehaansn and B.C. Bh»tt

А°ЗТПЛС<Пм minimi» aaasuraole do» for 250*0-15 aln pra-annesled LiF (Jfe, Cu,P)

phoiphor wae eetlaatsd to be 10 /iOy. The inability of the phosphor to a»amir» « t i l l

l o u r done for the ebore pre-snoealing treatment are dismissed. The pboipbor « в

found te exhibit a пш-xidlation induced TL peak at 355*С wbioh waa partly suppressed

by th» flea of K2 «aa during readout. It sas found ttat for о м hour of sunlight

exposure (at an intensity of 48,000 lux) tte fading caused In a gaasm irradiated

aaapl* m 2«í whioh ia» «ipilf loantlj- l . s» tban that ob»aiT»d in C a ^ i i y phOEpbor

(70)C) in th» elai lar conditions. The induoad TL signal dua to an ОТ (253.Т na)

•ipoaur» of 2.27 x 1O5 Jm'2 >«• found to t>» aqnal to that lnctaotd Ъу 0.7 «Су of Co

«aama >aya. Th* TL apcotnm of tb> phoiphox whloh ooom-a at Зб2гш for 25O*C-15 «in

pra-am»al»d aanplt «bifta to J94 n> for te» phoaphor wbicb l e pra-anmal*d at }25*C.

5. NAME ANO MAILING ADDRESS OF ORGANISATION OOING THE И

MTiaion of Hadlologlcal Proteotlen,ВЬаЪпа Ateailc ^search Cantra,ТгоаЪау, ВошЬау-400 065.India.

1- ASSOCIATEO ORGANIZATIONS)

Sapartatnt of " t a l c №*rgy, India.


Itptrtaant of Itoaic Aargy, India.

FROM.TO

October 62. .»«. 82

Î0. STATE OF ADVANCEMENTPROJECT - RESEARCH IN PROGRESS -PARTIAL OH FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6. DESCRIPTORS OR KEV Л 0 П

LiFilfe, Си, Р

AND HS-USABILITY CBiBlCTSRJSTICS OF LIP

(afe, Си, Р) TLD PHOSIB0B

2 BROAD H i д о ^

Doslmetrj

Bhuwim Chandra, A.R. Laxebaanai, R.C. Ihatt and K.G. Tohra

Preliminary Inreatlgations on the TL characteristics of LiF (fcg, CutP)TLD

phoaphor ar» reported. The aaln doeiaetric peak of thia phoephor ooours at 2?5*C

and l ta TL sensltlTlty to gaama radiation la 1.4 and 38 tl«e» higher than that

(if CaSO.iBy and Lii (TLB-100) reapectiTely. Ite TL aenaltWity iestrongly dependent

on te ape rature and duration of annealing. 3y reading in a TL readout cycle upto

J25*C the TL aensitiTlty of the phoaphor falla to about 25> of l ta original

sensit iv ity. Номт*г, by annealing the phosphor at 25O*C for 15 alnutea, i t »aa

posaible to regain thi ori.4nal eenaltlTlty. ftoton energy dependence and re-uaa-

b i l l t y characteristics are also reportei.

Ъ NAME AND MAILING ADDRESS OF ORGANIZATION DOING T

BlTislon of Badiologioal Protection,•babba itoelc Re oe aro h Centra,Trombay, loaba/-400 085


Ispartaant of i toa ic Energy, India.


B»parta»nt o f A t o a i c &>»rgy> I n d i a .

FROM'TO'

Jan. 82March 82

10PROJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION


LiF (ag, Cu,P)

TLB

Bhmran Chandra, A.E. Lakamanan, B.c. Bhatt and K.0. Tohra, Badiation Proteotle

Dosiaetry, Vol. 3 »o. 5, 1 9 « p. 161-167.

INDIA IAEA/HPRA/No.11

* A review on the rol* of thermolualnescent Dosimetersin fast-neutron personal dosimetry".

2. BROAD HEADING

Dosimetry

A.B. Laksbaanmn

ABSTRACT

In» review о е п я tb* intricacies involved 1я fa»t-neutron thermoluminescent

dosleetry (Т1Л). Ям Important ro l . of albedo dosimeters ( LiJ> * 'LIT pair) and

tfaeir limitation» ax* analysed. In* advantages of 2-liit TL system suoh aa tt»

250*0 peak i n LlF:mg, Ti and 210«C paak in CaJ?2:Tm m i the conrenticnal 1-hlt TL

system for hlgh-LET radiation dosi»mtry ar* stressed. The development of Irradiation

-oross-linked polyethylene ( П * ) , a heat-resistant proton radiator, la outlined» A

«.thod la suggested to xeduoe the background TL fro» IH5. Finally, the adrantagaa of

TL aot lnt lon d«t*otor* for hl«h energy neutron dodaatry ara pointed cut.

4AWE AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

Division of Radiological frotatlon,

Bhatiha Atomic Deseareh Centre,

ТгошЪау, ЪтЪшг-W 085, India.


Department of Atoalo Bnergy, India-


Hepartaent of Atomic Energy, India.

FROM /J«n. 14 82TO- .РеЪ. 1982


6. DESCRIPTORS О

High LETC«F2<Tm

UFlMg, Ti

11. REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM T H I S LABORATORY

A.R. Lakahaanan, Duel. Tracke, Vol. 6 Ко. 2/3, pp. 59-78, 1982


"Thermmluulneeeanee of 2 Centres in Id? (ТШ-100) atEler&ted Irradiation lamperatures

2 BROAD MEADII

Doalimitry

A.B. I«kahmanan, Btrawan Chandra, and R.G. Bhatt

Elevated irradiation temperature studies with LIP phoaphor and a cr i t i ca l

review of the Z centre model of Bink and Koe reveal that th* oorreUtion in the

lnteneity riee of «ie 285'C peak {peak 7) and Zj bend at T ^ . - 215'C «ported by

Sartla 1» a conmequenea of the Increaee in tb» TL inttnaiir of peak 10 (»400'C) . The

correlation in the TL intonaitlee of peaks 7 end 10 i* anticipated btoauee these

two реакв аг1ве due to the thermal lonizatlon of Z2 and Zj centrée, respectively. A

review of tbe Tari ou о experimental data and the models proposed Indicate that the

changes in TL eensitlvi-ty of peake 7 and 10 with T l r r at high dose level» may ariee

primarily as a result of structural change» in the crystal l a t t i c e . At low dose levelc

further etuâleeare propom»d to te s t the other two mechanism proposed in t l i s connec-

t ion for peak 5, namely trap competition and clustering of impurities.

NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WOR

Division of Radiological Protect ion,Bbabha Atomic Se search Centre,Trombe/, Bombay-400 085India.

7 ASSOCIATED ORGANIZAT IONS!

Department of Atomic Energy, India.

SPONSORING ORGAN

Department of Atomic Energy, India.

FROMTO

Hay 62July 82

PROJECT RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6 DESCHIPTORSOR KEV WORDS

Zj Centres, Z, Centres

1EFEFIENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUEO FROM THIS LABORATORY

A.B. Lakshmanan, Bhuwmn Chandra, and R.C. <ha.tt, Phys. stat . so l . (a) 75. 263


ел

Ямаркагеакяае ал* pketeetiaulatee Itaiaeaoeaoe af CaSO iDj

labeaeea prtjtkjleae ilaoa at eleratea1 teaperature far fait

a«*tren iealaetiy

2 BROAD HEADING

4. ABSTRACT

CaSO.iBj eabeííeí aelythjrleae «Пса were prepared ana their nkeepaereeeenee

ta* pk«t«.etlataatea laelaeaeenee * u teatea. Tka pkvapkereaeenoe «да pkete-

atlnuatea lwlneaeenee (FSL) eutpit af CaWyBjr •>• fennl ta lncraaae wltk tka

teaperatu» af atiauletlen aad recant, i t ?2*C tke ML eutyat af 0.6 am Шок

CaSOjiHr pelyetkyleiie *iaoa waa faon* ta be abaut 30 ttaea lta autput at raaai

temperatura. The alnfcra aeaaoraMe °Ca gava гаг ал< 14.7 «еТ aeneenergetle

neutras iaaea are eetlaatea ta be 3.5 aOjr ani в mthr, re«ptotlvriy.

5 faAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

BlTlalae af Baalalegloal FrateotiaaBkabka ttaala Хеааатвк Centre,ТгевЪау, BaabajWOO 085India.


DtpartMnt af Itaaio Kaarcr, Inala


Seiartaent af Ataala barer, India

FROM. ' June 83TO ' dmtlnuaa

PROJECT - RESEARCH IN PROGRESS -

PARTIAL OR FINAL REPORT WITH LIMITED

OR UNLIMITED DISTRIBUTION - REPORT



11. REFERENCES OP RECENT PUBLICATIONS IN SAME FIELD ISSUED PROM THIS LABOR ATO

1 T I T L E AND SUBTITLE

"Further etudle» en the Radiation Itoalastry Charaeterlatiee оïfaennolualneaeent -íCu Phoaphctr

2 BROAOHEAC

Eortmatry

HORS OR INVESTIGATORS A.B. Lakehaanan, Bhutan Chandra and B.C. Bhatt

Iifnatlgatlona on tea following radiation doslaetrlo oharaeterlatioa of

LI B.CLtCu TLE phoapbor an daacrlbad t (1) batch to bateb Tariation in TL

(ii)airurloUB lualnaaeanea affecta, ( i l l ) affeota of atoraga at asblent tanparatura

and humidity, and of pra-irradlatlon armaallng teitperatura on the TL aeneltiTlty, (IT)

dependence of TL aanoltirlty on tbe irradiation te^ieratun, (т) reuaablllty «apeota,

(vi) exposur* re TL neponaa and expoaus rate dependanea to 253.7 na ÜT radiation

and (vii) fading of radiation induced TL on axpouure to Bunli«ht.

NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE V

Division of Radiological ftrotection,ВЬаЫк Atomic ^search Centre,ТголЪау. ВовЬау-400 085 •India.

Department of Atoaic Enargjr, India.


Departaent of Atoaic Enargy, India.

9 DURATION OF

FROM

TO

/ Oct. 1981' «от. 1981

10PROJECT - RESEARCH IN PROGRESS -

PARTIAL OR FINAL REPORT WITH LIMITED

OR UNLIM1TEO DISTRIBUTION - REPORT


TLD

A.H. Lekehaanan, Btaunn Chandra and U.C. »hatt. Radiation Protection Soelaatiy7ol. 2 Ho. 4p. 2J1-259.

Оч INDIA IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11

TITLE AMD SUBTITLE

"Aaalytloal picture ef ike effect ef teaperatur* treataeat

• 1 Т Ы №•• ray eeaattiirity «f f af2-baaa« TU lasiaetry

3. AUTHORS OR INVESTIGATORS A.S. Х^аеаалавс1 S.C- Matt

ABSTRACT

CaF..baa»« ТЫ treats* at Ы«к temperature lm air azklblt a kigk lntrtaaloteeraelvaiaeseeaoe te TJT railatlens. Епетег, thla teaparatora t n a t a u t natestkw lmatialtli* te leaiilag raJUtiena. Tke laoreaee lm tteraelMlneseenceeeaaltlTHy 1* skew» te be «ue te tbe preawtlea ef exlie at the TU Material aurfaee,«>•»*• tk* retvotlea la / i » - sensitivity la attribute» te a ehaage in tb> nature•f lapurity atom reepemlbli fer TL ealaalen.

•ivlalea ef laiielegloal FretestlaaMuftha Attale «eaearok <wt»a,Srsafcar, Hrtay-400 0*5,Issla

bpartment ef iteaic Buzgy, laila.

В SPONSORING ORGANIZATIONS)

Jepaxtmt ef Ateale Snergn Inala.

9 DURATION OF

FROMTO'

March &.April 82

10 STATE OP ADVANCEMENTPROJECT - RËb-ARCH (N PROGRESS-PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

O E S C R i P T O R S O R K E Y W O R

A.S. Fradhaa mi U.C. l a a t t , J.Pbye. 9:Appl. Fhya. I<(1?«5)55-5»

"TL Emission Spectra ot Dy doped TLD»2 BROAD HEADING T*

DoBiaetry

3 AUTHORS OR INVESTIGATORS A.S. РгадЬап, Bhuwan Chandra and R.O. Bhatt

Т!Ы:я studying dosinetric properties of CaSO.:Dy and ag.B.O iDy we observedthat the TL emission spectra of thaae two TLDs worn recorded by increasing theresolution powar of the aonochroaator, we» reaaxkably different. To verify «betterthis difference i s due to the presence of undieolosed seneitiier added to agB.O_:Dy(Yugoslavia aakej preparation procedure patented), we pre axed By doped (0.5 l o wftgS CL and studied the eaisslon epeotrua along with CaSO :Iy,CaF2iDy and OaP2:T»and CaSO.tTa. TLTJs.

4

The emission spectra of By doped *gV>7, °aS°i and CaF, are not identical andeo i s tbe case with Та doped CaSO. and CÎÏg. Therefore, while interpreting the TLresults for Its better understanding on the basis of TL ealBsion epeotrua care should

be taken to note that even rare-earth TL eoission speotrua undergoes a significantohangs depending upon the crystal In which i t i s doped) and both the ealssion peakposition and relative intensities are a strong function of the host aaterial.However, the main splitting of Dy renalns in the rarje 450 na to500i» due to

trans i t i on and from 55О na to ~r na due to 4F,9/2

NAME AND MAILING ADDRESS OF ORGANIZATION DO

Divis ion of Radiological ProtectionBhabha Atomic Besearch Centre,Trombay, Bomb«y-400 085India.

ASSOCIATED ORGANIZATIONS!

Department of Atonic Energy, India

8 SPONSORING O R G A N I Z A T I O N S

Department of Atcnlc Energy, India.

FROMTO

June 1965ing. 1965

10 STATE OF ADVANCEMENTPROJECT RESEARCH IN PROGRESS-PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

D E S C R I P T O R S O R K E V

CaP.lTa

llsriSaahan BhuwwiOhandra" "тй НЛ.° BhatV, bit.Isotopes 1985 (In press).

Bad iatlon


•Fut Mutron doaimetry mslng CaSCysm, embedded

teflon din"

2 BROAD HEADING T

Dosimetxy

S.S. Shinde and R.C. Bhatt

CaSO.sXm TL phosphor embedded teflon dlacs were ustd to estimate thefait neutron finança a»d doaa Ъу TL activation method. The TL fading correction

dur Jl« aalf irradiation of phosphor after fast neutron irradiation was estimated

to be O.007b"1. Tba self irradiation t i e can be varied depending on the

f u t mutton doea which oan be roughly known by the phosphoreeoence emitted at

room temperature Ъу the disc immediately after annealing at 500*C. This

aathod can be furthar extended to estimate thermal and lntemedlate neutron dose

almultenously by Including a cadmium covered disc*

5. NAME ДЧО MAILING ADDRESS OF ORGANIZATION DOU

Slvialon of Radiological ProtectionBhabha Atoalo Re «a arc h CentreTrombay, ВсшЬау-400 085

Department of Atonic EnergyIndia

SPONSORING ORGANIZATIONS)

Department of Atonic EnergyIndia


FROM:TO

./ 1983

. / .continuing

Ю STATE OF ADVANCEMENTPROJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION


CaS0.:lta, Teflon discs,Fast neutron. TL activa-tien tPhosphore sconce

"See Deslaetric Paraaatere af Vt»A.iT>T sintered I*lletsand CaSO.iIy Teflen Bleos • A eeapirative stuay.

2 BROAD HEADING

lealaatry

P.P. Szabe, A.S. Pradhan and lauwan Chaacra

The effeot of DT ana sun-light expesurea en mgB.CLiDy aaá CaS0.:Ojr haa beenétudie*. Bath pneepbers are feunt ta кате intrinslo sensitivity te rjt radUtlonand their gamma ray inauoea TL fates faster if expesed te «mlight. The intrineiTL reepense fer an ÏÏT( 255.7 n») expesure af I500 3wT£ waa fauna avivaient te thatcaused by 1 mCy and 5 mGy e f r » Ce gamma raya fer HgB-O-iBy amu CaSO.iBy,reapeotively. The fadins cause, by 4M00 I«x ef sanlîgftt expesur. »*• « .7*and 5*£ In agB.CL:By pellets and CaSO cDy disos respeotively. %B4O7:Dy pelletédid not exhibit aay added «dvaatage over OaSO Dy teflon dlace exoept its«ear tiasue enulvalasoe.

NAME ANO MAILING ADDRESS OF ORGANIZATION DOING T

Division ef Badielogical Protection,lhabha Atemio Keeeerch Centre,ТгавЬау, la»bay-400 O»5. Imila.

Hepartnnt ef Atatlc inergy, Inala

8 SPONSORING ORGANI2ATIONISI

Department of Atemic *»rgy, India.

FROMTO

Oct. 62

Nor. 62


DESCRIPTORS On >•

TLTJ aiacsIntrinsic TL

00 INDIA IAEA/HPRA/No.11

i q U X U B R I U U CHARGED PARTICLE SPECTRA IN A Flf f MEDIA

UNDER 14 I0EV NEUTRON IRRADIATION

2. BROAD HEADING

DOSIUBTRY

Bhatia, D.P .ft Nagarajan, P . S .

4 ABSTRACT

Equilibria* «pectra ot charged secondaries ( alpha particles, and heavy

recolla ariaing from ( a, alpha) , ( n»n) and (n,nprine) éventa) in air, carboo-

di-oxide» tott tisaue and elemental media like carbon, nitrogen and oxygen, are

calculated for 14 MeV neutron irradiation. This work involves , in all, 43 indi-

vidual nucltar event types in C,N and 0, considering (п,Ц,), (n#<*t) , etc. аи

aeparate éventa, and similarly the inelastic scattering events leading to

different excitation level» are considered separate events. Available angular

distribution* ara taken in to account» This work arises in the analysis of the

results of calculations of responses of a carbon-carbon di oxide and a tissue—ti

вsue equivalent gas ionisation chambers models* Both the dose- and fluence-ате-

ragad L E T'a art also computed*

5. NAME AND WAILING ADDRfSS OF ORGANIZATION OOING

Division of Radiological Protection

Bhabba Atimic Research Centre

Bombay 400 086 f INDIA

ASSOCIATED OflGANlZATIQNISl

8 SPONSORING ORGANIZATION^)

9 DURATION OF

PROMTO

/June 1983

10.PROJECT - RESEARCH tN PROGRESS -PARTIAL OR FINAL REDORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

Equilibrium spectra

Alpha

Heavy recoils

Uean LET'S

14 MEV

11 BEFEOENCES OF RECENT PUBLICATIONS IN SAME F U ISSUED F

ITALY IAEA/HPRA/No.11

1. TU"Reference radiations for calibration purposes" Uosimt'try

3. AUTEURS OU CHERCHEURS

R.F. Lai tano, S. Di Matteo, Л. Divina

. ntsyMçThe experimental a c t i v i t i e s for the s t anda rd iza t ion of reference X глс!ы|Лопь has be

c a r r i e d on. Most of these r a d i a t i o n s which are based on the ISO recommendations a re

ENEA, Radiation Metrology Laboratory, C.R.E. CasacciaP.O.B. 2400, 0Ü1U0 Roma, I t a ly

10. tRF.CH£KChE £N CO'JRS -

4f РГ-ОЧТ PARTIEL CZL~ZZГ^ГЗ АDIFFUSION'r-T253^Ü P .L î ' . ' l ï LE-RAPPOST SÜUft"S POUR FO3UCATION

6. f

Reference RadiationsCalibratîonX-ray dosimetry

Standardízzàzione,mediante misure assolute di esposizione, di alcune serie di radiaziorX raccamandate dall'ISO.Atti del 23° Congresso Naz. dell'AlRP (1983) - ENEA,Serie Símposí

ITALY IAEA/HPRA/No.11 ITALY lAEA/HPRA/No.n

Here are reported the results of an experimental investigation carried out during theast 3 years, on the neutron sensitivity of TL phosphors. 13 different types of solid TLdetectors (chips, ribbons and disks) of commercial grade were included in the experiment.The irradiations were performed using narrow spectra of fast neutrons in the range 0.6-5 MeV, and wide spectra from a thick beryllium target (mean energy 7.5 MeV) and from a

252-Cf source, with accurately known neutron and gamma components.

The results in free air are in fairly good agreement with the data available in theliterature. The sensitivity coefficient kU of 6-Li and of B-based dosetneters at the sur-face and inside a water phantora are much higher than in free air, as expected fromthermaiizing properties of water. A further increase was obtained when the detectors wereexposed into a tissue-equivalent container.

The results indicate that the neutron-gamma discrimination by the classical twin-detectors technique could be based upon the use of 6-LiF, Li borate or, perhaps, Mgtetraborate, as neutron-sensitive phosphors, and 7-LiF or Ca-based TLDs as neutron-unsensitive dosemeters.

1 . TITHE kTSOUS-TJinC

"New experimental data on the sensitivity to fast^neutrons

of a number of sintertd commercial TL phosphors"

G. Scarpa

LE5TRAVAUX

ENEA ,- Dosimetry and Biophysics Laboratory, C.K.E. CasãCCLP.О-В. 2400 - 00100 Roma, Italy

6. sounci

ENEA

9 . OU «EC DU PROGRAMME

DE:..- /...J5S0

A : J

10. E- Rf.CMERChE EN CO'JHS -

RiPfOHT PARTIEL С 2 5 Л З ^ Э АDIFFUSION g r - T f l m g ; ILLIMITEE -RAPPORT SOUMIS POUR PUBLICATION

6. D£5C*'rTEUR5 OU «OTS С

ThermoluminescenceFast NeutronsTL Phosphors

Dose Measurement in BeO Detecto

Thermoluminescence

by UV Traribferred Dos 1me try

G.Susuoli, L.Lerobo, R.Nanni, I.Sermenghi

BeO detectors have high sensitivity tû UV radiation, particularly for transferred TL.

Some experiments have therefore been performed on BeO TL dosemeters in order to obtain

data on the reassessment of the dose for irradiated and read-out dosemeters. This techni-

que is useful in practice as it can prove the reliability of the assessed dose value,

particularly in cases where the values are relevant. A 15 W UV germicidal lamp has been

used for these experiments and the method has been checked m the dose range from ъ mGy

up to 0.2 Gy.

After the UV irradiation, a pre-read anneal at 140°C was performed on the detectors in

order to erase low temperature peaks.

It has been proved that transferred TL is linear over the whole explored dose range and

the transferred signal is about 30% of the direct one. The minimum dose which can be

reassessed by this technique is of the order of 5 mGy and the precision is of the order

of 15-20% at a dose of 20 mGy.

The fading both for direct and transferred TL has been measured and in the case of tran-

sferred TL, the time elapsed is that oetween the first readout and UV irradiation. In

fact, some delay is expected between the first and second dose reassessment. In both

conditions fading is the same and practically negligible, at least during a time interval

of sixty days.

ENEA - Dipartimento PAS - Lab. Applicazioni di

C.R.E. E.Clementel

Via Mazzim 2 - 40438 BOLOGNA (Italy)

6. [

- TL Dosimetry- Personal Dosimetry

o * - . .• •."<••>

Г ' "i ' L t ' - .

_ . . . . ' ^ ' .

- f . r t n_ , - ..-• ' i : '. ' i

" . :'.'_ ."

" 5 —

CE -

AT 1Г ••1

•j Lt V ; M ; occ.iNt

О ITALY IAEA/HPRA/No.11

Low Dose Measurements with lyoluminescence MaterialsDosimetry

G 4 Busuoll, L.Lembo, F.Monteventi

The LL reader assembly, set up in the laboratory, has been improved in order to stan-

dardize the measurements procedures and to limit the uncertainties. Materials, like

L-glutamine and N-acetyl-D-glucosamine, in addition to mannose and glucose, have teen

tested using sensitized solutions heated and kept at constant temperature during the

read-out process. M&nnose is rather insensitive even using sensitized solutions (mini-

mum detectable dose: 0,1 Gy), while the detection limit for glucose and N-acetyl-D-

glucosamine is of the order of 2 mGy using luminol as the sensitizer. The reproducibi-

lity is within +_ 10% for doses of the order of 50 mGy for glucose.

Measurements with diphenylisobenzofuron {DPBF) have shown small amplification of the

lyoluminescent signal.

FNEA - Dipartimento PAS - Lab.Applicazioni di Dosimetria

C.R.E. E.Clementel

Via Mazzini 2 - 40138 BOLOGNA (Italy)

E N E A

oc _ i..

A • J...,

10. ClirO'AVAMCiMCM:

ЙГ^ЛЛ1 - hi C^íbCnr ZK COURS -R/4T-O:iT РЛЯ NEl ÇZt^Z^I.'-^^J A

RAFPOî'.T GOUV'^OIM Г .'3Î.1CATION

- Dosimetry- Lyoluminescence

ITALY IAEA/HPRA/No.111. 11ТЯЕ I T ЬСи'.-ТПЛЕ

New Organization of the Personal Dosimetric Service

2. йуамои: o

Oosimetry

G.Busuoli , A.Cavallmi, L.Lembo, R.Nanni , I .Sermenghi

At present the dosimetric service of ENEA runs about 12000 dosemeters per issue period

for X- and gamma rays. The design of the automatic system has therefore been dimen-

sioned on the above quantity which will remain practically constante in the future due

to the strategy adopted by our organization'.

Three automatic readers on line with a computer are foreseen. Each reader will also be

equipped with a printer so that, in case of operational faults of the computer, the

readout data can be printed and afterwards manually loaded on the computer through the

video terminal units. These units (4 of them are foreseen in the system) will be used

to interact with the central computer in order to update customer files for each period

m order to modify, if necessary, the dose data and handle the purely administrative

work. In preparing the dosemeter çíh automatic apparatus will read the identification

label on every card dosemeter and feed these data into che computer in order to couple

each customer and his code; afterwards the computer will print a label with different

information for the customer (name and surmane, issue period, year, etc.). Both these

labels and the card dosemeters are automatically loaded in a packaging machine, which

already contains the filter elements, and produces the complete pack by welding the va-

rious parts in a plastic envelope. The manual operations are therefore limited to load-

ing the magazines which are put either in the readers or in the automatic packaging ma~i t i 1] j ^ *Ь Н h Ь ^ rf*' f j *

ENEA - D i p a r t i m e n t o PAS - L a b . A p p l i c a z i o n i d i D o s i m e t r i a

C.R.E. E.Clementel

Via Mazzini 2 - 40138 BOLOGNA ( I t a l y )

- RïR/.P."'O4T Р-'ОТ! US.ON Г™

£*CM£ EM COURS-iEL tT^S^r.î-"a^3 A—S«.î5 I'-Li'." . ЕЕ -

ГL'BUCATION

pg

"*"1' f j г6.

- Standardization

- Personal Dosimetry

ITALY IAEA/HPRA/No.11 ITALY IAEA/HPRA/No.11

rntercomparison and Standardization of National Dosimetric

Services

2. PUDB eu: с ».

Doslmetry

J. AUTEL^'S пи с» cr:t>tjns

G.Busuoii, A.Cavaliini

LÊS THAW u«

ENEA - Dipartimento PAS - Lab. Applicazioni di DosimetnaC.R.E. E.ClementelVia Mazzini 2 - 40138 BOLOGNA (ItaiyJ

О'. - Л

TTVM - RE-CHÜftChE EN COURS -

* ÎLLlMirCE -R PUBLICATION

OU MC "S L S

- Standardization- Personal Dosimetry

Measurements of Indoor Gamma Doses in Italy

G.Busuoli, L.Lembo, R.Nannt, I.Sermenghi

Indoor gamma dose measurements have been carried out in different areas in Italy using

TL dosemeters. This preliminary campaigne has evidenced some peculiar situation particu-

larly in the area of Rome where the data are dispersed over a wide interval (up to a

This can be due to the different typology of the udwellinings and this parameter must

be carefully considered during future measurements on a larger scale. The possibility

to use LiF (TLD-1OO) dosemeters instead of CaF2 bulb dosemetee has been investigated both

for decreasing the casts and to reduce the drawbacks presented by the latter dosemeters,

like energy threshold, self irradiation and fading. The laboratory experiments confirmed

this possibility if LiF dosemeters will be issued for a period of 2 months due to

their slightly higher threshold dose.

ENEA - Dipartimento PAS - Lab. Applicazioni di Dosimetria

C.R.E. E.Clementel

Via Mazzini 2 - 4ЭД38 BOLOGNA (Italy)

..-•"F "..I ~tJ<JV«: Г ГГ L! f"i rijSLlCYiTION

- Dose to population- Environmental Dosimetry

l/lto ITALY IAEA/HPRA/No.11

Neutron Dosimetry by Etching Track Detectors

2. ш н ю к ' с ^

Dosimetry

G.Busuoli, O.Civolani, L.Lembo

Experiments have been carried out in order to determine the dosimetrie characteristics

of a fast neutron dosimeter consisting of a CR-39 detector coupled to a polyethilene

converter. Chemical etching has been used with a solution of NaOH 6.25 N at a temperatu-

re of 70°C. The energy response has been checked by using monochromatic neutrons in

the range 0.5 - Id MeV and radioactive neutron sources of Cf-252, Am-Be and Pu-Li. The

experimental results have shown that the energy dependence is of the order of +_ 30%

within the above interval. In order to improve the response in the low energy range

below 500 keV, some experiments have been carried out adding to the previous dosemeter

an (n,o( ) converter consisting of Li В 0 and using the albedo technique- Preliminary

results appeared promising for a practical application of the composite dosemeter in

routine dosimetry.

ENEA - Dipartimento PAS - Lab.Applicazioni di Dosimetria

C.R.E. E.Clementel

Via Mazzini 2 - 4QJ38 BOLOGNA (Italy)

4 •.?J-4 P. 31 iCATION

- Neutron Dosimetry

- Personal Dosimetry

JAPAN IAEA/HPRA/No.11

"Reference Japanese Man" Studies as a Model of Man for

Dosimetry for RadionuclidesReference man

studies for the

Japanese

Tanaka, G. and Kawamura, H.

Studies on physical and physiological characteristics of the normal Japanese

are in progress. Mass of organs, twelve for the male and eleven for the female,

daily consumption of various nutrients in the diet, daily intake and skeletal

content of some alkaline earth elements, and metabolic parameters for radioiodine,

i- e., thyroid uptake and biological half-life as Influenced by large natural iodine

intake from marine algae products were already reported.

Estimated weight of bone as well as Che distribution of mineralized bone in the

skeleton is being studied along with mass of cells near bone surfaces and active

red bone marrow in the Japanese in relation to the significance of these tissues as

source and target organs in internal dosimetry.

Distribution of elements in body organs and tissues as determined by trace

analysis techniques for tissues from the Japanese are also studied as metabolic data

for elements in man In relation to dosimetry.

Estimation is currently made on the collective dose equivalent in the Japanese

received from fallout strontlum-90, lodine-131, and plutonium-239 using "Reference

Japanese Man" data.

National Institute of Radiological Sciences

Laboratory for Radioecology

3609 Isozaki, Nakaminato, Ibaraki 311-12

Japan

Japan Science and Technology Agency

Reference man data

Japanese

Organs

Metabolic data

Elements

Iodine

Alkaline earth elements

DosimetryThyroid

Cortical bone

Trabecular bone

Source organs

Target organs

3ARTIAL On ?INAL ===OS7 'VlTn (.'MilOR UNLIMITED 0IS7?I..ui.ON - SE'OSÏUSMITTHO гОЙ PUBLICATION

1. G. Tanaka, H. Kawaraura and Y. Nakahara: Reference Japanese Man-I. Mass of Organs and

and Other Characteristics of Normal Japanese, Health Phys. 36, 333 (1979).

2. G. Tanaka, H. Kawamura and E. Nomura: Reference Japanese Man-II. Distribution or

Strontium in the Skeleton and Mass of the Mineralized Bone, Health Phys. 40, 601(1981


1. T(T(.; *«asueriT(.E

Dose Evaluation and Microdosimetry for the Radiation Protectior- I M M O N U I . . '

Dose evaluation i

- T.Maruyama, Y.Kumamoto, Y.Noda, H.Yamaguchi, A.Shiragai, K.Nishizawa

and K.Iwav

For the purposes of risk evaluation, the population doses from man-made radiationsources such as medical, occupational or environmental exposures have been estimatedon the basis of nationwide surveys on the frequencies and technical factors in the useof ionizing radiations and radioisotopes, using a phantom measurement. In order:tohelp the epidemiological studies of atomic bomb survivors in Hiroshima and Nagasaki, are-evaluation of neutron and gamma-ray for the survivors has been carried out within situ measurements such as thermoluminescent dosimetry of bricks and t i les. Mjcro-dosimetric studies have been performed for the determination of quality factor and forthe construction of mode? to evaluate biological effects at low level radiation exposure.Furthermore, the attenuation and scattering effects of various materials have beeninvestigated for the design of radiation apparatus and faci l i t ies.

National Institute Radiological Sciences9-1, Anagawa-4-chome, Chibashi 260 Japan

Science and Technology Agency

9. 3 U * * MOw Of

FROM- April 1981то-

Î3 Î T * r ï o« AO« л-ncirê — ' **ÍPZZJÍ-ZI - nascency, IN PROGÕ£=3 -

Population dose.Medical exposure,Occupational exposure.Environmental exposure.Organ and tissue dose,Atomic bomb dosimetry,Radiation shiejding,Microdosimetry,

L)2)

j)


"Depth riose -md Dieentri'* rield •

voshinori Inoue

4. AISTRACrThe Yield of l i icentrics induced by exposure of ii'iimn lyr.rhocytes

at various deoth in witer to Jo-60 •• rays w s studied.^lood Samples and 0.6 cm- chamber in latex sneith of IONEX

DOSR/DOSERATE PÔO/3 were fixed at 0, p, 10 and Ie? cm depth of 37 ' "water phantom(30 X 30 X 24 cm) and were exposed to 2% H oi 100 Cií'o-60 y rays .

Lymphocytes were cultured with a separated leucocyte technique.фпе supernatant(about 0.Ç ml) containing the leucocytes was added toa culture mediun consist ing of about 3 ml NCTC 13^, 0.1 ml РЧ -Мând a n t i b i o t i c s , "ulture was kept at 3? ' С in rm atmosphere of ^ 'Г0-1 for ?0 h. Colcemid was added 30 h after incubation.

c DicentMc yields at 0, ?, 10 and 1С cm depth in water v;ererespectively 0.00^1(1 dicentric/Pi^J- examined c e l l s ) , 0.00?7( 1Ü./133O ),0.0130(3/616} and 0.0101(10/939). A peak in dicentr ic yield wasobserved at 10 cm deDth in water.

Japan Atomic Energy 4eser-trch Ins t i tu te ,Tokai-nura , "a/.a-gun, Ibaruki-i-ren, 31^-Japan

FROM: . 9 / .TO: J+/.-.

10. STATE OF AQVANCEMEST-WOJEC7 - RSS£AflCH IN PROGRESSчлрт1л^_ ър е(мЛ1_ af:pQHT WITH LI

E. OESC

Depth DoseIjicen.tric Vie IdЧипчп Lymphoc yte:o-60 v rays

NETHERLANDS IAEA/HRRA/No.11 NETHERLANDS IAEA/HPRA/No.11

Development of a thermoluminescence based personal

2 . BROAD HEADING

DOSIMETRY

1

Lautenbach.G.

4 ABSTRACTThe beta-energy dependency and the shallow dose response of a personal thermolumine-scence dosimeter (TLD) have been investigated.

For various beta-ray sources the depth-dose distribution in different materials asperspex, PTFE and aluminium has been measured using thin (0.13 mm) LiF teflon dosi-meters.

The beta-response of thin LiF teflon dosimeters placed behind absorbers oí \ and5 rag/cm2 was studied for different angles of incidence and various beta-raysources.

As a result of the investigations, i t was decided to apply a LiF teflon disc of0.13 mm and a 0.4 mm disc of CaSOi, : Dy as the beta sensitive part of the personalthermoluminescence dosimeter which is under development at ECN.


Netherlands Energy Research Foundation (ЕСЫP.O.Box I, 1755 ZG Pctten, The Netherlands.

8 SPONSORING ORGANIZATIONS

9. DURATION OPPROGRAMME

FROM- . / 1.981TO ../.[.982

HHÜtEBXR- RESEARCH IN PROGRESS -

therrooluminescencebeta-rays

Calibration of a whole body counter equipped withHPGe-detertor,

2 BROAD HEADING

DOSIMETRY

A.S . Kever £ ing Buismdn

The I£CN-Whole Body Counter lias r e c e n t l y been extended with a High Pur i ty Cerm.mium.- ray d e t e c t o r . The e x c e l l e n t r é s o l u t ion of t h i s instrument leads to а чепн i t í v i t ycomparable to the formerly used Na l -de t e i : t o r s , whi le improving the i d e n t i f i c a t i o nof incorporated r a d í o n u c l i d e s .

C a l i b r a t i o n and de te rmina t ion of the minimum d e t e c t a b l e a c t i v i t y of Che new s e t - u pлге in p r o g r e s s .

NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORi

Netherlands Energy Research Foundation (ECN)

P.O.Box I, 1755 ZG Petten, The Netherlands.

SPONSORING OHGANIZATiONIS)

9 DURATION OF

PROGRAMME

FROM. 1.983TO . ' .1983

SEARCH IN PROGRESS -

radiation protectionwhole-body counting

NETHERLANDS IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

1Л

rrzRADIATION DOSE TO THE PATIENTS IN DENTAL X-RAY EXAMINATIONS

an in v i t r o and in vivo investigationOptimization

of Radiation Protection

VAN DER STELT.P.F., RUYS.P.N., EOERSMA.H., ZHIGT.A., VAN DER LINDEN,L.W.J.

Although individual radiat ion doses in dental radioqraphy are rather low, the numberof examinations in the population is large and s t i l l increasing. Dental radiographymay substant ia l ly contr ibute to the c o l l e c t i v e dose.Better understanding of the dose d i s t r i b u t i o n to patients in dental radiographyf a c i l i t a t e s the weighing of benefits and r i s k s . Data from l i t e r a t u r e are widelydiverqent.In t h i s project the dose d i s t r i b u t i o n s during several dental X-ray proceduresand radiat ion protection techniques are studied. I'easurements are carr ies out inan a^epted version of the Alderson-Rando phantom and in vivo, by means ofthermoluminescence dosimetry ( L i F ) .

5. NAMb ANO MAILING ADDRESS OF ORGANIZATION Dl

DEPT. ORAL RADIOLOGYSCHOOL OF DENTISTRY/ FREE UNIVERSITYP.O.BOX 71611007 MC AMSTERDAM


DEPT. OF RADIOTHERAPY/ FREE UNIVERSITY HOSPITAL

NETHERLANDS DENTAL ASSOCIATION


DUTCH FUND FOR HEALTH PREVENTIONDUTCH GOVERNMENT/ MINISTRY OF PUBLIC HEALTH

FROM-01,1981TO 12/1987

10K - RESEARCH IN PROGRESS -

PARTIALJOflíKKÍAK REPORT WITH LIMITEDeBxUMKKíKCCXDISTRIBUTlON - REPORTSUBMITTED FOR PUBLICATION

Radiation protectionDental RadiologyDentistryRadiologyDosimetry

taW^ absorption coefficientsof dosemeter and t issue material in oral dosimetry.Dento-Max.Fa*- -Radio"!. Suppl .5:19 (1983)•Kwee,H.T.,Van der Ste1t,P.F.,Van der Linden(L.W.J.,Ruys,P.N.,Zwigt,A.,Boersraa,H.: Compari-son of phantom measurements and in vivo measurements for dosaae assessment in oral radio-diagnosis.Dento-Max.Fac.Radio! . Suppl.5:20 (1983)

European neutron dosimetry intercompanson projectENDIP-2

ПОДО Hf ADiNG

Dosimetry inter-compansons

3 AUTHOPS OR INVESTIGATORS .

J. Zoetelief , H. Schraube , J.J. Broerse1 and G. Burger2

ABSTRAI: Д p r e r e q U j s i t e f o r radiobiological studies is that the energy dissipationin the irradiated material be determined with a sufficient degree of accuracy andprecision. In addition, for calibration and testing of radiation protection in-strumentation accurate and precise dosimetry is required. Within the frameworkof the Commission of the European Communities two neutron dosimetry intercom-parisons namely ENDIP-1 (1975) and CENDOS (1977) have been carried out. Theresults of the ENDJP-1 intercomparison revealed dose discrepancies up to about20 per cent betwepr. different participating groups (EUR 6004). The CENDOSsmall scale intercomparison (EUR 6567) indicated improvement in dosimetry re-sults for three groups which obtained considerably differing results in theENLIP-1 intercomparison. During the past eight years considerable efforts havebeen made to obtain more reliable basic physical parameters and to improve theexperimental techniques used for dose determinations.

In the ENDIP-2 program, dose measurements are made with lonizationchambers and a Geiger-Müller counter at 18 institutes in the neutron fieldsactually employed for radiation protection, radiobiology and standardization. Themeasurements concern neutron and photon kerma free-in-air and absorbed doseat various depths in a water phantom. The results obtained by the ENDIP-2measuring team in the neutron fields and the reference photon beams are directlycompared with those obtained by the host institutes and will be reported in thecoming year under full identification of the participants.

NAME AND MAILING

J. ZoeteliefRadiobiol. Inst. TNOP.O. Box 58152280 HV Rijswijk,The Netherlands

ESS О ORGANISATION DOING ТнЕ ЛQflK

H. Schraube2

Inst. f. Strahlenschutz CSFIngolstãdter Landstrasse INeuherbergFRG

Gesellschaft für Strahlen- und UmweltforschungIngolstãdter Landstrasse 1Neuherberg, FRG

SPONSORING ORGAM^A

Commission of the European Communities

FROM 0483T ° 09' 85


6 OËSCRITOHS DR KE Y WORDS

-neutron dosimetry-ionization chambersGejger-Mûller counters

-standardization-radiation protectionand radiobiology

TiONS IN SAME [LO ISSUED FROM THtS f.

J. Zoetelief and J.J. Broerse (1983). Dosimetry with tissue-equivalent ionizationchambers in fast neutron fields for biomédical applications. Phys.Med.Biol., 28,503-520.

ITHAILAND IAEA/HPRA/No.11 UNITED STATES OF AMERICA IAEA/HPRA/No.11

Î. TITif AND SUBTITLE

Personnel and Environmental Radiation Dose Monitoring

2. BROAD HEADING

Posxroetry


Thongmitr^W; Wanitsuksombut.W; Rativanich.N.

Environmental gamma dose was investigated by TLD-100 of Harshaw Chemical Company.The average annual dose was 0.9 mSv.

Radiation Measurement DivisionOffice of Atomic Energy for PeaceBangkhen, Bangkok 109Û0, Thailand

Office of Atomic Energy for Peace




FROM. Щ\ ContinuingTO .. /.

10.PROJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

DESCRIPTORS OR KEY

Personnel f'onitoringEnvironmental gammadose

OAEP Annual Report 1982

TITLE A«osu«nn.e DOE Tersonnel NeutronDosimeter Evaluation and Upgrade Program

1OJ.D HCAQINCi

PersonnelNeutrontosimetry

3. AUTHORS on INVESTI с*.тол5 Leo G. Faust, Dennis E. Hadlock, Larry VI. Brackenbush,Mary Ann Parkhurst, George U.R. Endres, Edward J. VaTlano (DOE)

"Af*ersonnel neutron dosinetry has always been d i f f icu l t because of theindirect methods of dose assessment, the extreme ranges of energy response ofthe dosimeter, and the wide range of neutron energies routinely encountered(0.025 eV to 10 HeVj. This program has been identified to provide a continuingeffort to resolve problems of assessing personnel neutron dose and doseequivalent at DOE f a c i l i t i e s . Substantial progress has been accomplished,including an assessment of the current status of personnel neutron dosimetersystems at DOE faci l i t ies, recommended methods of calibrating personnel neutredosimeters, and continuing development of several concepts that show promise сupgrading the state-of-the-art in personnel neutron dosimetry. A continuingimplementation phase has also been identified to pursue objectives of thisprogram that wi l l enhance personnel neutron dosinetry at DOE facil i t ies andprovide the opportunity for transfer of program accomplishments to DOE con-tractors. Provisions are also made to provide the opportunity for vendors totake developed prototypes and transform them into commercially-available dosireters and/or instruments.

Pacific Northwest LaboratoryBattelle Memorial InstituteP.O. Box 999Richland, Washington, U.S.A., 99352

Lawrence Livermore National LaboratoryUniversity of California at BerkleyUniversity of Connecticut

United States Department of EnergyOffice of Nuclear Safety

F*CM- 19/80тс . ./ongoing

S3»c«ÎfJc>«Wi6O(SiJôWW^»»ï'%v 2 jot УХ s » XiOfic хкях

NeutronOosimetry/DosimetersEnergy ResponseDosePersonne]

McDonald, J.CW. ; Response Characterist ics of Splected Personnel NeutronDosimeter; PNL-3982.Val îa r io , E.J . , L.G. Faust, M.A. Parkhurst; Ninth DOE Workshop on PersonnelNeutron Dosimetry; PNL-SA-10714.

UNITED STATES OF AMERICA IAEA/HPRA/No.11 UNITED STATES OF AMERICA IAEA/HPRA/No.11

E AND SUBTITLE

l-i Measurement Kvaluai 1 ami Upgrade"

2 BROAD

i - r s t i n i l

lose t o >Un ( i n t e r n a l and

TORS Thomas. H- t'bD e n n i s h . H

ji, Lick M. b e l b \ , O o r g e W.K. h n d r e s .

4. ABSTRACT

T h i s p r o g r a m is f o c u s e d o n t h e r e s o l u t i o n of L h e p r o b l e m s a s s o c i a t e d w i t h t h e f i e l dt h e br il l

and inbirumtntb used .it Dût f a c i l i t i e s are bi-inp evaluated and cha rac t e r i zed . Theinvest igat ion i nr 1 udes 1 Í an assoísmenc of mpdûrcment .s уяК'гтгч now in u st'.2) development »f improved c a l i b r a t i o n systems and procedure;., 3) a p p l i c a t i o n ofinnovative beta doiimetry concepts , 4) inves t iga t ion ot new instruments or concept.G

for monitoring and spectroscopy, and Î ) preparat ion of a "manual o£ f>ood p r a c t i c e "to assure an adequate beta measurement program.

5 NAME AND MAILING ADDRESS OF ORGANIZATION DO

Bat t e l le NorthwestI'.O.liox 999Ríchland, WA 9^352USA

7. ASSOCIATED ORGANI2ATION(SI

Kansas State UniversityInternational Sensor Technology


DOE

FROM: ДО.91TO . / . Open

10. STATE OP ADVANCEMENT

XKXHÍEX - RESEARCH IN PROGRESS -

Dosimet rvSpectraCa 1 ibratfonlust ruments

11 BEFERFNCfSpF RECENT PUBLICATIONS IN SAME FIELD ISSUED FG.w.FC. Yndres, P.L. Roberson, TheAppIicat югП #* r* • £ j _ i i _ - _ i _ . i i "^ —'—* ' —

IËLD ISSUED FHOM THIS LABORATORY p

l i f a Multi-Element Beta Dosi1 Ж- 1 • Scherpe I Z ,

Pacific Northwest Laboratory. Presented at the International Beta Dosimetrv Sympoïium,Washington, D.C., February 15-18, 1983.2) Cf..Simons, R.B.btuewe, T.M.Debey,K.D.btansbury, Application of Beta Doaimetry Research,Kansas State University.Presentiat the International Beta Dosimetry Symposium, Washington, D.C., February 15-10,1983.

Conceptsэ SUBTITLE Rad ioloj'i c i 1 Phys ics .in Radiation P r o t e c t i o n

nti Microiiosimetrit 2 BHDADHEADJ*

Dosimetrv

MOHS OR INVESTIGATORS J - W. Влит and Ï1. N. Varma

fiabii' сопсерСй л nti knowledge1 arc developed in areas of mdioJ»>jit;ji physit^4 ABSTRACT t t ) pI4ivitj l_. n „C>UIUJ yxperimfntíil .ind tlieoreticaJ l'iuindat inn ! or iintlt±i\stiindim',In phv.sifal, i-honii al and biolnîi-.i 1 rflationsliips between аш гц" deposition, due toibborption of loni/.ing rad iatum, .ind suh'-4'i,uent bioloîi .il ni fticts.

Aicur.ite v.ilues lor iundnnu'iital dosinu-trie quantities are determined usinsinique exper i tient л I cquipraent and lieavv-ion .icceicrattirs, Computer cocies are developed to

correlate the physical and biological data, and to test mathematical models and theories ofiobinlogical action.

Two new theories of radiobifloyical action were developed and tested againstspecific sets of biological data. The f i r s t , a hit-size weighting theory correlates well

ith mutations induced in Tradescantia by a wide spectrun of radiation qualities. The••coud, provides a biological and anal vtical franicwork to explain dose-response relations

for tumor induction in Sprajiuc—Püwltív r.4ts, and provido;; ins i&lit into a median isn whichcan cause larê population heterogeneity. Accurate measurements of stopping power andenergy to form an ion pair fU) have slmwn and confirmed that l-'-valut-s , îcrâsi1 witli de-

mises in ion vulocitv and inc-ro.isc with increase in atonic number.

Additional data for comparison with theorotifal models will be gathered andd tu test , extend, and rvi ine tftc maclienatfcnl models of riîdiobiuJngical action.

'ihis worU will lead to development of a sound technical and scientific basisfur: radiation protection, risk assessment at low do-;es and dest,- rates, health protectionstandards, and greater understanding of mechanisms of biological damage due to ionizingradiation.

LING ADDRESS OF QRGAIN ZATlON DOING THE WORK

ionSafety and Environmental Protection DiBrookhaven National LaboratoryUpton, NY 11973

RGANIZArfOMSI DOE

FROM. /1965TO . /cont inuing

6 DESCRIPTORS OR KEYWORDS

Dosimetry, Microdosimetry,Modeling of Bioeffects

7 I . REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

Varma, M.N. Calibration of proportional counters in microdosimetry. Presented at LÏIEEighth Symposium on Microdosiraetry, Julien, West Germany, September, 1982,

Varma, M.N. and Bond, V.P. Empirical evaluation of cell critical volume dose vs. cellresponse function for pink mutations in Tradescantia. Presented at the Eighth Svmposiumon Microdosimetrv. Julich, West Germany, September. 1982.

Bond, V.P. and Vanna, M.N., A stochastic weighted hit site theory of cellularradiobioloyical action. Presented at the Eighth Symposium on Microdosimetry, Julich,West Germany, September, 1982.

Varma, M.N. and Bauin, J.W. Auger ulectron characteristic energy loss spectrafor electro-deposited americium-2ul. Nucl. Instr. Methods (submitted).

Baum, J.W. Clonal theory of radiation carcinogenesis. Presented at the EighthSymposium on Microdosimetry, Julich, West Germany, September, 1982.

f00 UNITED STATES OF AMERICA IAEA/HPRA/No.11

Rongelap and I'tirlk Dose Reassessment

2. BROAD HEADING

Assessment ofHose t o Man

L e s s a r d , E. T . , i l i l t e n b e r g e r , R. P . , Naidu, J . R.

4. ABSTRACTTRACT

Since March 1954, persons who have resided at Rongelap and Utirik Atolls in

the Marshall Islands have been examined by medical specialists to determine if any

observable effects occur as л result of exposure to radioactive fallout From United

n and (4) extrapolation of fallout components based on studi

the radioactive fallout which fell on a Japanese fishing vessel in the vic-ini

the test. The conclusions drawn from this study are not vet definitive, howe

this re-examination lends to thyroid absorbed dose estimates 2 to 10 times gr

than originally estimated.

Safety fi Environmental Protection Division

Brookhaven National Laboratory

Upton, N'Y 11973

7 ASSOCIATED OHGAN1ZATION1SI

8. SPONSORING ORGANIZATION'S)

department of Energy


FROM 11/ 79TO / C,ontlnutrte

RESEARCH IN PROGRESS -

RDS

Thyroic! \bsorbed ^ose

Radioiodine

Fallout Contamination

Lessard, Г. Т . , M i l t e n h e r H e r , R. *>., Cohnf S. " . , v , , S O H n o , Г.. V. am1. Conard, Ч. A19Í>2, "Pro t rac ted Fxposure to ^a l lou t : The Rongflap and ' ' t i r i k Experience", to hepublished in Health Physics

UNITED STATES OF AMERICA IAEA/HPRA/No.11

Marshall Islands Radiolopical Safetv Program InternalFxposure Prom Cs-137, 7.П-65, Sr-9n, re-5"j and Pti-214In Marshall Islands Resit'-tints

2 BROAD HEADING

PersonnelMonitoring,

VESTIGATOHS

F.áwa rd T. Les чага, Robert R. МП tenber%er, Stephen V. "nsolino and Tohn И. Baum

A ABSTRACTrrom .Tune 1946 to August 195P, the U.S. Department of Defense and Atomic Fnergy Commis-

sion conducted nuclear weapons tests in the Northern Marshall Islands. Prior to the com-

mencement of the testing program In 1946, 167 bikini Atoll inhabitants were moved away

from their islands which were to be used as the initial site for nuclear explosions- In

1^47, the 145 people of F.newetak Atoll were relocated from their islands which were even-

tually to be used as the second major test site. On March 1, 1^54 an ahoveground test

(BRAVO) at Bikini Atoll produced high levels of radioactivity, some of which subsequently

fell on Rongelap and t'tirik Atolls due to an unexpected wind shift. The 23a inhabitants

of these atolls were relocated and were subsequently returned in June 1954 to "tirik and

June 1Q57 to Rongelap. Many Rikinians later returned to reinhabit their atoll from I

Q7P

to 197P. The Fnewetak people began to repopulate their atoll in 19^0 following an exten-

sive radiological survey of their islands. Measurements of individual body burdens and

activity excretion rates have heen obtained following rehabitation of these four atolls

and continued measurement occurs at Enewetak, Rongelap and I'tirik. These data are used to

estimate the individual and population committed effective àose équivalent. The conclu-sions o r this study to date are: (1) the dietary intake of Cs-137 is a major componentcontributing to the internal dose equivalent for the years after fallout contaminated theatolls, (?.) the long-term biological removal rate constant for Cs-117 in the Marshal losepeople Is in agreement with that observed in L'.S. and British populations, am1 is a func-tion of body mass, (3) for persons whose diet includes fish, 7.П-СЛ is a major component ofcontamination hv fallout, (4) radioactivité in the daily intake is decreased at a rategreater than that due to radioactive decav alone, and (5) for Rongelap, 1'tirtk and formerBikini residents who reinhabited their atolls, the internal committed effective dose

equivalent exceeds tîie extprnal dose equivalent by a facperiod. rew reliable Pu-H39 measurements on human excretentive data leads to the conclusion4 that a reliable es

of Pu-?39 as neasured by btnitted effective dose eqt

The impacttimate of

or of two during the rehabitationa were made. An analysis ofipiate of activity intake requiresoassay techniques, has not been

f.-aient. Current research focusetfurther research.included in the eson fission track etch measurements and improved rat]iochemical separations in order Lomeasure at tht- 1 fCi (3.7xlrt~5) level in urine. A liquid scintillation photon-electronrejecting alpha spectrometer with pulse rise time discrimination has been built to .

measure Pu levels in fece-s and teeth.

Text cent, on p.


(con'tj

1Л

Safety and Environmental Protection Division

Brookhaven National Laboratory

Upton, New York 11973

department of Energy

FROM-

TO' / .Continuing

10. STATE OF ADVANCEMENTPnOJg&T - RESEARCH IN PROGRESS -PARTIAL OR FINAL ПСРОПТ WITi I LIMITОП UNLIMITED DIBTniOUTION—ПСРОП8U8MITTËP ГОП PUBLICATION

6. DESCRIPTORS ОП KEY WORDS

Uhole-Rûdy Count inp,Bioassay

Pal lout Contaminât ion

Greenhouse, N.A., Miltenberger, R.P., Lessard, E.T., 1Q80, "Dosimetric Results for the

Bikini Population", Health Physics Vol. 3B (May) pp. P46-851.

Lessard, E.T., Miltenberger, R.P., Г-reenhouse, N.A., 19P<\ "Dietary Radioactivity Intake

From Bioassay Data: A Model Applied to 137cs Intake by Bikini Islands Residents",

Health Physics Vol. 39 (August), pp. 177-1P3.

Miltenberger, R.P. Greenhouse, N.A., Lessard, E.T., 1980, "Whole Body Counting Results

from 1974 to 1979 for Bikini Island Residents", Health Physics Vol. 39 (Sept), pp. 395-407

Miltenberger, R.P., Lessard, E.T., Greenhouse, N.A. 1981, "60co and

1 3 7C s Long-term

Biological Removal Rate Constants for the Marshallese Population", Health Physics Vol. 40

(May) pp. 615-623.

Lessard, E.T., Mlltenberger, R.P., Cohn, S.H., Musolino, S.V., and Conard, R.A., 1982,

"Protracted Exposure to Fallout: The Rongelap and Ucirik Experience", to be published

in Health Physics.

II.OPERATIONAL RADIATION PROTECTION TECHNIQUES.

RADIATION LEVELS

61

IBRAZIL IAEA/HPRA/No.11

?. TITULO V SUBTÍTULO DEL K*OGflAMA

DEPTH ABSORBED DOSE DISTRIBUTIONS FROM HIGH ENERGY

ELECTRON BEAMS"

2. TEMA GENCHAL


Cecatti, E.R., Malamut, С , Almeida, C.E.V.

4. HESUMEN

A study of the depth absorbed dose distribution in an

homogeneous medium irradiated by electron beams with energies from 3 to

20 MeV was made taking into account the influence of the beam energy,

the energy spreadt field size and design characteristics of the

accelerator.

Although the electron beam from the accelerator may

be initially approximated to a monoenergetic and monodirectional beam,

the passage through the various materials in the beam, i.e. scattering

foil, transmission chamber, implies in a significant energy and angular

spread.

Three accelerators with different .scattering and

col1imation systems were studied leading to different depth dose

distributions. The slope of fall-off region of the depth do&e curves as

well as the surface dose values are the parameters which have *»bowen

some variations.

A theoretical model was constructed in order to

explain the increase in the depth dose in the build-up region with the

increase of the energy, taking into account secondary electrons.

5. ,

Instituto de Radioproteçao e Dosimetria

Caixa Postal 3702522602 - Rio de Janeiro - RJ Brasil

DE ...07/8.1А ..О5./83 ....

AC1ON

ХШКОКМГ,

INFORMÊ PRESENTADÛ PARA PUBLICACION

6. i

electron beam

accelerators

dose distribution


QUALITV CONTROL IN RECTILINEAR SCANNERS AND

DOSE CALI IRATORS IN RIO DE JANEIRO - IRAZIL

Ж

3 AUTORES O INVESTIGADORES

MENDES, L. AND íEG£T, A.

4. RESU«£N Rectilinear Scanners and dose calibrators were tested for a variety

ifif operating conditions and performance. The tests for rectilinear scanners

were based on image quality obtained with phantoms -f the brain, liver and

thyroid. The paramètre investigated for rectilinear scanners included the

direct control of the operator, such as the proper setting of the focal

distance, the velocity, the photopeak calibration, contrast and background

count. The accuracy of the dose calibrators was checked with sources of

Cs-137, Co-57 and Co-60. The linearity of dose calibrators was checked with

sources of technetium~99ni and geometry was likewise checked witth variable

volumes of technetium-99m. The evaluation of the proper s*etting for rectili-

near scanners was made by determining the number of hot and cold areas in

the phantoir, before and after corrective adjustments of physical parameters.

The results obtained in 30 rectilinear scanners and 10 dose calibrators

indicate déficiences in the operating conditions (rectilinear scanners) and

performance Bose calibrators).

5. NOMBRE Y SEftAS DE LA ORGANIZACION OUE REALIZA EL TRABAJO

INSTITL'TO DE RADIOPROTEÇAO E DOSINETPIA - COMISSÃO

NACIONAL DE ENERGIA NUCLEAR - IRASIL.

COMI5SÃO NACIONAL DE EMERGIA NUCLEAR - IRASIL

01 f 82PROYECTO - INVESTfGAClON EN CURSO -INFORME PARCIAL 0 FINAL CONDlSTRlBUClON LIMITADA O NO LIMITADA -INFORME PRESENT ADO PARA PUBLICACION

6. DES

Quality Control

Rectilinear Scanner

Dose Calibrator

Phantom

BRAZIL IAEA/HPRA/No.11 CANADA IAEA/HPRA/No.11

1. TITULO V SUBTÍTULO DEL PROGRAMA

Thermoluminescent Properties of Brazilian Topaz

2 . ТЕМА GENERAL

ÏÏThermoluminci.cence


Ferreira Lima, CA., Hosa, L.A.R.. Cunha, P.G.

4. RESUMEM

The aim f this work is to study the thermoluminescent properties of transparent colorless

topaz ((hi(F,OH))-$i.O^ from Governador Valadares, state of Minas Gerais, Brasil. Topaz

samples were chosen with masses ranging from l8mg to 24mg and sises close to (3x3xlmiti).

Before irradiation they were annealed at ДОО^С for 30 minutes. This was sufficient to

eliminate residual natural radiation TL. The TLD reader used was a Karshaw 2000 A + 3,

with nitrogen purging. A typical glow curve presents 2 "eaks at 120?C (oeak 1) and

l859C (peak 2) respectively. A small peak at about 80«C can also be detected ,

incorporated to peak 1- A post-irradiation annealing at l20^C for 15 minutes completely

eliminates the peaks at 80?C and 12(^C, leaving peak 2 unchanged. The TLD response was

not studied at temperatures above 300-C» Peaks 1 and 2 show a linear behaviour in the

dose range 7-420mGy for a sample irradiated in a Studsvik reference dose irradiator

65273 (90gr -90у). The peak height method was used. A linear behaviour of peaks 1 and

2 was also shown for samples irradiated in a Co-60 irradiator from 1,29 x 10-2 c/XG to

2,58x10-1 c/XG (50Я to 10003). The fading behaviour of peak 2 was btudied ut to 15 days.

The rate of fade of peak 1 is higher (**» 30% in hours). The sensivity of the topas

samples is « 150 times smaller when compared with LiF - TLD 100 Marshaw. This work

shows that topaz crystals possess favorable TL characteristics. The use of topaz powder

is also under investigation^

Instituto de "adioproteçao e Dosimetria

Caixa Postal 37025

22602 - Rio de Janeiro - RJ - Brazil

7. ORGANIZACION U ORGANIZAClONES ASOCIAOAS

L DURACION DEL PHOGRAMA

DE. W..J.JI

tO. SITUACIDNPROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL 0 MNAL CONDISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARAPUBLICACION

TopazThermoluminescenceHosimetry

Measurement of the Mixed Exposure of an Operator to Radio-active Aerosol and Quartz in the Confinement of a MiningEquipment Cab

Ope rat íonal RaProtection Techniques.Radiation Levels


MARKHAM, J . W . , Y O S H I D A , K .

ABSTRACT

Work in high grade ore situations, found in Saskatchewan, Canada, requires the use of

specialized shielded and ventilated vehicles to provide the equipment operator with

adequate protection from external gamma radiation and a suitable supply of filtered

air. This study assesses the benefit of the filtered-air cab to workers in the

context of tie total working environment in the cab, i.e. relating to internal and

external sources of ionizing radiation, radioactive and non-radioactive dust (including

quartz), noise and thermal conditions.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING T

Dept. of Social and Preventive MedicineUniversity o£ SaskatchewanSaskatoon, Saskatchewan, CanadaS7N 0W0

7.

Saskatchewan Research Council

SPONSORING OHGAI

Saskatchewan Department of LabourAtomic Energy Control BoardCluff Mining


FROM 9/»DTO .3/82

10

PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

assessmentdosimetryaerosolschemistryphysicsradiation protectionexposure

I

FINLAND IAEA/HPRA/No.11 FRANCE IAEA/HPRA/No.11

en

Field Measurements for the Quality Assurance of X-Ray ImageIntensifier Télévision Systems Used in Medicine

2 ВЯОДО HEADING

Operational

Radiation Protection

Techniques

II

H e i k k i l a , M.J., P i r i n e n , M.A.

4, ABSTRACT

Routine checks of fluoroscopy installations have revealed wide variations in patient

exposure rates, which is partly due to the poor performance of the image intensifier

television systems. This project was set up to develop standardized methods for

qualitv assurance in the field, to specifv the performance of individual components

in the image intensifier television system and to clear up the situation in Finland.

Until summer 1983 a total of 250 image intensifier television systems were tested

and the results are under consideration.

N A M E «


P.O.BOX 268, SF-00101 HELSINKI 10

FINLAND

8. SPONSORING O H C A N 1 2 A T I O N I S I

9. DURATION OFPRbOHAMME

FROM- « / §0TO ' ? / . «

га s™-PROJECT - :PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTE

6. DESCRIPTORS OR KEV WORDS

Image intensifier

Quality assurance

Fluoroscopy

Radiation protection

I. m u i i i iounn>i Détermination du facteur de qualité et mesure|2'de l'équivalent de dose des champs mixtes neutron et gamma -Compteur Intégrateur de Rayonnement Complexe С I R С Е

Techniques de Radio-protection -Niveaux de rayonnement.

NGUYEN Van Dat, RiCOURT Alain, PARHENTIER Nicole

A. >itsu"c L'acquisition et le traitement rapide des informations permettent de réaliser Гег,semble compact C1RCE pouvant donner instantanëmeot en une mesure unique Têquivalentde dose,la dose absorbée,le facteur de qualité et l'évaluation des fractions de doses dues respectivvement aux neutrons et aux photons. Le principe u t i l i sé est basé sur deux idées essentielle:portant : - d'une part sur la substitution possible du transfert linéique d'énergie Lj pari;hauteur des impulsions h\ délivrées par un compteur proportionnel ; - d'autre part sur letraitement impulsion par impulsion au fur et à mesure de la production d'événements dedépôts d'énergie au niveau du capteur. Ainsi, à chaque impulsion h-j correspond un transfertlinéique d'énergie Lj et un facteur de qualité Q( l j ) . La dose absorbée D, T'équivalent dedose H et le facteur de qualité Q sont alors donnés par les formules suivantes :

= x I h .

où С est le facteur d'étalonnage et m est la masse gazeuse contenue dans le volume sensibledu compteur.

La dynamique des impulsions est de quatre décades (1 mV - 10 V), ce qui nécessitedeux voies identiques de traitement des signaux . L'une des voies t r a i t e les impulsionsdans la gamme de 1 mV à 156 mV après avoir été amp l i f i ésd 'un facteur 64 ; l 'au t re t r a i t eles impulsions dans la gamme de 156 mV ã 10 V ne subissant aucune ampl i f icat ion.

Des mesures effectuées dans des faisceaux de_neutrons monocinétiques de 22 keV à16 MeV montrent que les facteurs de qual i té e f f e c t i f s Q suivent de façon satisfaisante ceu:recaimandes parlCRP 21. La gamme de sens ib i l i té est de l 'ordre de 10"6 S v h ' l à K T 1 Sv h"1.

INSTITUT DE PROTECTION 4 DE SURETE NUCLEAIRE -Département de Protection SanitaireB.P. 6 - 92260 FONTENAY AUX ROSES (France)

INSTITUT DE PROTECTION & DE SURETE NUCLEAIREDépartement de Protection Technique

Commissiriat ã l 'Energie Atomique (CEA) / 'Commission des Communautés Européennes (CCE)

D Î . ~ 1980

* •— 1984

HE EN COUBS -

- DOSIMETRIE- RADIOPROTECTION- NEUTRON- PHOTON- FACTEUR DE QUALITE- EQUIVALENT DE DOSE

1) ^44: ?Ít.5ffi45-.4Q.'!Vra445Í4íto»№(FflRD. U.K.. {1980) p 625-636

2 ) Proç.,8th .Sy.mpos.onJlic/pdo.sAm.e.tr.y.,. .OJJJJfH. F.R.G. (1982) p. 1087-1098.

3 , Congres Commun Italq-Français fie Radioprotection - FLORENCE,ITALIE (1983).

* selon le

ON INDIA IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11

A low Lnal Baden Detection Syatea

s r l r M t a r a О.Г., fiagharayya »., Hua i.H. and totrappa Ï .

X staple and portable ayatea for iha aeasureaent of тегу low concentrations ofradon bas Ъаап deTeloped. l l r la auplad in a 24 oa dia i 11.5 oa cylindricalchaaber and tha f*e»hl» foraed !a i atoa» ara oollaoted on s negatiTely oharged discfor 90 ain. Th» total alpha counts obtained oa the collector diac during anoptiaiaad poat aaapling delay intarnl of 1-75 «in are used to coapute the radonooneantrationa. The alnlaua detection l i a i t for this syetea i s 1.7 Bq/ш'. Thealrataa can be used for the aeasureaent of radon in breath, in dwellings and inanrironaental aaaplaa.

D MAILING ADDRESS OF TICJN DOING THE ЛОВ

Bhaoha itoaic Research Centre, Health Physics Unit,Jaduguda, Slnghbhua, Bihar,India


Shabha itomic Raaearoh Centre. IAEA

RGANiZATiON'Sl


FROM- ./1Э82то- . . / .1.934

- RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDОЯ-UNLIMITCD DISTRIBUTION fiEPQftT

RadonDosinetry

Air Monitoring

Radiation Surrey of Uranite Mine at Jeduguda U.ing Eleotrata

2 BROAD HEAOlNGII

Operational RadiationProtection Techniques

HOfiSOR INVESTIGATORS

Eotrappa P., Dua 3.E., Khan A.H. and Stmaeundarw s .

Heaaureaente of tlae-areraged concentration of radon daughters and tradiation lerela «ere carried out in the uraniua nine at Jaduguda using alpha andganaa electret doeiaetars dereloped reoentl; in Health Pbyeiee Division, BiRC. Theeffective doae-equivalent ratea Taried from в.2 pSr/h to 40 nSr/h (4.0 шгевА)depending on the nine eleTation. It ia dnonstrated that this new technique proTide»an accurate and convenient method for conducting radiation aurreya in a uraniua minet

compared to existing methods.

NAME AND MA

Health Physics Divis ion,Bhabha jfttomic Reaearch Centre*Bombay 400 085.

8 SPONSOHING oUGûNlZATiOMSl

Bhabha itoaic Research Centre

FROM-TO

' 1982M 983

10PflOJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6 DESCRIPTOHS OR KEY WOHDS

Uraniua Mine,DosiaetryElectrets, Radiât ionSurrey

Report Но. ШС/1-756 (Кот. 1982)


Serelopaent of threshold Detection Technique for measuringleutron bergy Spectra

2. BROAD HEADING I I

Operational RadiationProtection Technique*Radiation lerele

Xhasnabit B.H., Sarkar P.I. and Muthukriehnan S.

ABSTRACT

A threshold detaotion technique Ьаа Ъеап deTaloped for aeaeureaent of neutron•paotra is high intensity mixed fields In the Ticinity of Bedim or high energypartiel* «ooeleratora. The method с onsists of Beasurlng the lnduoed gaaaa actirityon foils of euiUble eleaente aad arriTing at the neutron ap*otn»i fro» the oroesaeotion data. HowsTer the rnabir of threahold detector» that are атаНаЫе for thepurpose i* small Halting the points at which the flux can be sraluatsd. Theuoosrtalnities ID the oroaa aeetion data ax* also a source of error.

To aolT* this problea the seroeth order approxlaation of the speotrua la aadeby expanding the flux in a set of orthonoraal funotioas constructed from the crossaeotion data. With this approximate spectrum at the centre, a randoa search iainitiated отег a finite hyperdiaenalonal apace oontaining a set of possible spectra.Only thoae epeotra whloh whan refolded with the cross section aatrix gire theaotlTlty ralua within the error l ia i t are acoeptad. Among these the one that yield»the aaxla.ua information entropy ia aelected aa the final apeotrua.

A method for dealing with the mcertainity in oroaa section data is indicatedwhich will be incorporated in future. Keutron speotrua fro* Tantalus due to theboabardaent of 40 Мет alpha particule» baa been estiaatad using the еЪоте aethod.


Health Physio» Unit,ТЮЗ Centre.I/A* Bilhan Vagar,Calcutta 700 064.

aoabaa Atoaio leetaroh Centre


FROM- . . /1.982

TO .. Д 9 6 4

PHOJCOT - RESEARCH IN PROGRESS -

ОП UNLIMITED 013ТЖТШЛ

-SUBMITTED ron PUBLICAI


neutron spectroaetryThreshold DetectorsAccelerators

"Inrentory of ioniua (Th-230) during uranium processingand i ts implication» on operational limit» Operational Radiation

Protection Technique»

Surya Rao В., Lakahaanan A.B., Bhexathan Aygngar, Iriahna Rao Tand Viavanathan S.

Uraniua oxide plant proceaaaa aagneeiua diuranate for the production of pure U0..The effluents froa the plant hare Shown significant leTele of lonlist (Th-230). InTlew of i ts high radiotoxicity. a laboratory study was carried out to estimate itedistribution in YorioUB proceas streams, full paper presents the analytical procedureseaployed in the study. The distribution of ionium in the process streams shows that itfollows uranium streaas-aamoniom diuranate carries' the aaximua (95*). Fro* theaotiTity ratios of 10/0, reTieed SAC raluee Ьате been worked out using the rule ofmixtures. The present air actirity at uranium oxide plant has been found to be belowoperational limits and the presence of ionium does not pose any additional haiard.

IAME AND MAILING ADDRESS Of OHGAMlZATiON

Health Fhysics Unit.Nuclear fuel Complex,E.C.I.L. P.O.Hyderabad 500 762, I№IA

7 ASSOCIATED ORG


ШаЪпа At^aic Research Centre

9 OURATION OFPROGRAMME

FROM 8 , 1.981

TO 2./.1982 SU8MITTED FOR PUBLICATION

Uranium processIonium distributionSAC values

•

O00


1. . \,ч .

Characterization of ultrafine aerosols

G.Tarroni, C.Melandri, M.Formignani, T.De Zaiacomo, C.C.Lombardi

Ultrafine aerosols (particle diameter less than .1 ura) are widely produced in all pro-

cesses at high temperature and in decay of alpha active noble gases: they constitue

therefore an important problem by a protectionists point of view.

The behaviour of ultrafine particles (UP) is completely ruled by brownian motion and

their characterization consists in the determination of diffusion properties.

Some diffusion batteries (DB) are been assembled to cover the size range of interest

(0.002 to 0.1 ш т ) . Each DB consists of a suitable number of circular or square paral-

lel channels. In parallel a data reduction procedure is studied in order to avoid the

usual heavy procedure. The method is based on the separation of the two main parameters

(median diameter and geometric standard deviation) in a log-normal size spectrum.

ENEA - Dipartimento PAS

Laboratório Fisira e Tossicologia degli Aerosol

Via Mazzini 2 - 40138 BOLOGWA (Italy)

-Aerosol

-Ultrafine particles

-Diffusion batteries

DE- ...g... t, 1993.

А -„...б -'. -1984.


Size Characterization of Alpha Active Aerosols

C.Melandri, G.Tarroni, C.C.Lombardi, I.Formignani, T.Üe Zaiacomo

4. ntrvwt

Pursuing the activity devoted to a better characterization of the natural alpha active

aerosols, a research is started to cover the gap between the upper operating 1imit of

the instruments based on brownian diffusion and the lower operating limit of the ones

based on inertia.

For that a screen type diffusion battery is now in a stage of validation and calibration

with different types of diffusion elements at various fluxes. Moreover the inertial

spectrometer equipped with CR-39 track detector has been recalibrated in the size range

O.d-1.5 urn with monodisperse aerosols labelled with radon daughters. The sensitivity

of the method of track development and counting made it, possible to obtain the cor-

relation between particle size and alpha damage position in the plastic detector.

5. 1

ENEA - Dipartimento PAS - Lab.Fisica e Tossicologia degli

Aerosol - C.R.E. E.Clementel

Via Mazzini 2 - 40138 BOLOGNA (Italy)

7. 1

;ГПГ.-ЗГГ.Г. ILLIV1ÏCÎ.-

-Aerosol

-Rn, Th daughters

-Diffusion battery

-Inertiaï Spectrometer

POLAND IAEA/HPRA/No.11 POLAND IAEA/HPRA/No.11

TITLE A N D SUBTITLE

Ionisation chamber for a; olica'ion in measuringcystcm for ostinr.'.infî -at lent risk duringX-ray diagnosis.

Z i"O*O HUOINE

RndiationProtection

3. AUTHOR* OA INVESTIGATOR»

K.Zawanowski ,!î. ZarucSci

AlSTKACT

S":in doBc neasurenenhel

S;:in doue measurements Tor patient during nn examination '.vithhel» of ionisation cViP.raber.The response or chamber is independenti'ron qi,c lance between pa lient and X-rsy tube and also irradiatedarea.Designed on$ constructed equipment and measurements results arepresented.Tcchnolofical and construction parameters were speciallydeterminated for i1* work conditions.Heasurenent system gives the ЛЬ.-itnl response suitable for father data processing.

5 NAME A N b WA1LINC ADS'ESB Of OKCAMUATION DOtMC THE WOMK

Central Laboratory ' o r Sadiolo^ical ProtectionKonwaliowa 7,05-194 Warsaw,Poland

B. SPONSORING O U A M | £ A T I O N < S )

Polish Atonic 3nerL~y Agency

9. QUKA7ÉOM О

MOM: OJ/I9B1т о • -

Я. ГГАТ1 о» AOVANCIMCN-fROJECT- í

SU»MrTTEB FOa "UBL1CAT10N

Ionisation chanborS>in doseX-ray diagnosis

1. TITul ANO SUtTJTLE

Alpha - spectromctrical system for low-levelradioactivity counting .

II2 . t f tOAD HKADIMC

OpeiatiozmlBadiatien ProteoticaTechniques.

Andrzej Pietruszewsîrij Andrzej 3ar3iiski, Jan Ja.7ielak

AtSTRACT

А1р]гл spectrometrical system was designed and constructed forIT, Th and Pu determination in environraental sanples , " " " \-'+-~consists of - e lectro l izer for seven simultaneously working sites -couplet of platiniun electrodes aad special saapling bottles-» «casu-renent system of e i rht vacuum chambers with si l icon surface barrierdetectors . Spectra are registered with help of multichannel analyserPlurimat - 20 and Tiixer router systems. Sadiochemical method ofseparation transuranium elements and electrodeposition on stainlesssteel discs i s performed prior to alpha counting. Routine measurementsof Pu-239,240, Pu-238, Ü-233, J^234 concentrations in a i r dustsamples were started from 1932 a t the sanpling site at Warsaw withhelp of alpha spectrometry.

5. NAME AMO-*n«tLINC AOOKEXS ° * ОЯ%д«ККАТ1ОМ OOINC TMf WOM

Central Labûratory for Hadiolo-ical Frotection

7. AÏ5OCIATCO ORGANISATlOMCSl

B. f'ONSORIMC ORAANiZATlONES)

Polish Atonic Energy Agency

9. OUAA7rON ОГ

."О0ЯАММЕ

«O«:../.1.981TO: ../.1983

6- OSSCRIPTORS OK Cf T WOHOS

Alpha spectronetryLieasurement system

CI.OR reports

о SOUTH AFRICA IAEA/HPRA/No.11 SOUTH AFRICA IAEA/HPRA/No.11

TITLE AND SUBTITLE

FILTER TESTING OF LARGE VENTILATION SYSTEMS

2 BBOAD HEADING

OPERATIONAL RADIATION

PROTECTION TECHNIQUES

LEUSCHNER, A H; PUTTER, H D; ROSSOUW, J W.

Test methods of the filters in large ventilation system are being investigated.

The use of alternative aerosols to those of the standard test methods are :----~

• • • ' ' •- - • • • • l a r g e

be a good aerosol for detection of leakage through HEPA filters.

5 NAME AND MAILING ADOHESS OF ORGANIZATION O O I N G TMt uVOR*

NUCLEAR DEVELOPMENT CORPORATION OF SOUTH AFRICA (PTY) LTD

PRIVATE BAG X256

PRETORIA

0001 SOUTH AFRICA

SPON5OH1NG ORGANlZATtON(S)

FROM I , 83TO i i ' 84

STATE OF ADVANCEMENT- RESEARCH IN PROGRESS -

DESCRIPTORS OB REV

FILTERS

AEROSOLS

VENTILATION

FILTER TESTING

Filter testing of large ventilation systems.

Leuschner, Л H; Kruger, J; Putter, H D. Annual Congress of the South African

Association of Physicists in Medicine and Biology. Cape Town 14-16 March 1983.

TESTING OF AIR-CLEANING SCRUBBERS AT 1'RANIUM PROCESSING

PLANTS

ПОАО не ADlNG

OPERATIONALRADIATION PROTECTIONTIXHNlQUrS

LEUSCHNER, Л H; PUTTER, H I); ROSSOUW, J U,

Practical test methods arc investigated for the determination oi the efficienciesof air-cle;ming scrubbers.

lîFc, vapour which is released into a i r is converted into solid compounds of uraniumand HF. The efficiencies of the sen hbers for the solids, are then determined fromthe rat io of the upstream concentration to chu downstream concentration of uraniumsol ids, as determined from grab samples taken into fluorocarbon f i l t e r s .

The efficiencies of the scrubbers for HF aro calculated from thu НГ cunrenlr.itionsas determined by grab samples taken with midget impingers.

NAWt AND MAILING ADDRESS OF ORGANIZATION OOiNG ТмЕ WORK


PRIVATE ВАС Х256

PRETORIA

0001 SOUTH AFRICA

SPONSORING OHGA

FROM .1 82TO 12 8't

ттоавя RESEARCH IN PROGRESS

SCRUBBERS

AIR CLEANING

AEROSOLS

URANIUM

Leuschner, A H; Rossouw, J W; Kruger, J . T e s t i n g of a i r - c l e a n i n g s c r u b b e r s of

uranium p r o c e s s i n g p l a n t s . Annual Congress of the .South Afric.m Association of

P h y s i c i s t s in Medicine and Biologv, C;ipe Town, 1Д-16 March I98 Í .

SOUTH AFRICA IAEA/HPRA/No.11 UNITED STATES OF AMERICA IAEA/HPRA/No.11

REMOTE-CONTROLLED RECOVERY AND OBSERVATION VEHICLES

2 BROAD HfcADING

OPERATIONALRADIATION PROTECTIONTECHNIQUES

3 AUTMOR5OR INVESTIGATORS

KRUCEU, J; KRUGER, P J; LOURENS, P Ci PARTRIDGE, С A; NiRRIS, A D & IRVING, С F,

Л ABSTRACT

In support of a remote-controlled recovery vehicle (ABBA), which is cablccontcol ledand designed to perform light to moderate duty in high-hazard areas, a radio-controlled observation vehicle (ROT) is being designed and constructed. The obser-vation vehicle is battery-powered and can be controlled up to 0,5 km in air andthrough substantial com-rete shielding. It is fitted with a radio-linked televisioncamera, with a separate pan and t i l t control, and height adjustment.

NAME ANO MAILING AOOBESS OF ORGANIZATION DOING THE ЙОЙК

NUCLEAR DEVELOPMENT CORPORATION OF SOUTH AFRICA (PTY) LTDPRIVATE BAG X256PRETORIA0001 SOUTH AFRICA

NG ORGANIZATIONS!

FROM- . 1/ 78TO \2J 83

PARTIAL WHHKX. REPORT WITH LIMITEDHMtXKÍWKHXRR DISTRIBUTION - К Н Ш Х

DESCRIPTORS OH KEY WORDS

REMOTE CONTROL

RECOVERY VEHICLE

OBSERVATION VEHICLE

Health Physics Support and AssistancDepartment of Energy

OjUT.lt inn 11R.hüat ion J'rnc t'< t in

VESTlGATOHSJ.M. SelbyL.fi. Faust

ABSTRACT

Pacif ic Northwest Laboratory through the Htmlth Physics Support and Assist , тс сproject ib providing a major tee lmUal ro lo in Health Physics support, and ass i s tanceсо tiie Division ot~ Environmental Protect ion л ml Emergency Preparedness, Dep.ir Lmmitof Energy, on specia l t echnica l s tudies p r i n c i p a l l y assm U t e d with the .m.tlysis о Iimpact of s t a n d a r d s , r e g u l a t i o n s <mrf engineer ing and a d m i n i s t r a t i v e a c t i n n s onoccupat ional and environmental exposure. Technical s i u d i e s a re л Iso provided fors p e c i i i c subtasks or spec ia l sLiufíes i i lent i f ie í í .nul scoped bv DOE ,ts ,i p r i o r i t y ltt-mafter r.-view by PNL and DOE/RL.

Current subtasks under t h i s general support program inc lude: Evaluation ofDraft Standard ANSI N42.17 on Survey Ins t rumenta t ion , Evaluation of Draft StandardANS] N13.30 on Radiobioassay, DOE F a c i l i t y Emergency Preparedness, DOE AI.ARA Upgrade,DOE Program for improving Workplace Air Sampling and Monitoring, Evaluation andUpgrade of DOE In te rna l puslroetry P r a c t i c e s , Neutron Depth Dtise Study and Developmentof Neutron Ins t rumenta t ion .

Ba t t e l l e NorthwestP.O. Box 999Richlaml, WA99352, USA

ASSOCIATED •

DOE, NRC

SPONSORING ORGANIZA

DOE

FROM. 3 '79TO - / contin

JEBCKECT - RESEARCH IN PROGRESS -

Air MnnitoringInstrument Perform.miR.-iiliohinassayIntercomparison StudyNeutron Me.-t sur ornentPersonne] DosimetryEtnergencv Prep.irednes


TITLE AND SUBTITLETechnical Evaluation of the Capability of PresentInstrumentation to Meet the Draft ANST Standard onPerformance Specifications for Radi.ition ProtectionSurvey Instrumentation

2. BROAD HEADING

OperationalRadi.ition ProtectionTechniquesRadiât ion Levels

3. AUTHORS OH INVESTIGATORS

Kenoyer, J. L. , Swinth, K.L., Selby, J.M.

A proposed standard of the American National Standards Institute (ANST),Performance Specifications for Health Physics Instrumentation, is currently beingevaluated at Pacific Northwest Laboratory. The project involves developingprocedures for testing instruments, evaluating the radiological and environmentalperformance of approximately 100 instruments, and comparing their performance withthe requirements of the proposed standard. The performance specifications at-itedin the standard will be evaluated as to whether or not they -ire adequate ant!practical for currently available instruments.

Twenty-four test procedures have been developed to date. An environmentalevaluation laboratory has been equipped with an environmental chamber, a radiofrequency generatur, a pressure/vacuum exposure chamber, vibration tables, andshock-testing equipment.

NAME AND MAILING ADDHESS OF OflGA

Pacific Northwest LaboratoryP.O. Box 999Richland, WA 99352USA

IZATION DOING THE VYOR


DOE. NRC


DOE, NRC


FROM 9 / 8 1TO 10/ 84

10I - RESEARCH IN PROGRESS -анккмвккнгатоагтштшагашктшнхх:

«адшювиявяшюаовшжк

DESCRIPTORS OR <E¥ W

Health Physics

Instrumentation

Portable

ANSIStandard

RadiationProtection

1 1 . REFERENCES OF RECENT PUBLIÍ ' 'ONS IN SAME FIELD ISSUED FROM THIS LABOR ATOR

III.EFFECTS OF RADIATION

1. External and Internal Contamination. Human Data

73


St d M S í 1 • l'wiq Л Pc- m -i'-ls f r r a t U ' . t u c l l d f i n h a l a t i - n

LII n a n .

2 BROAD HEADING Ж-1Dosimotry.Assessment cf D' s.

t- Man (internal | .


W. HOFMANN, L. mBI-INGEF*' , F . DASCUP-, I . F E H É R ' ' , I . ВА1л'пНА7Л'+) , E. PDHL

4 AQSTFIACT.arge inter- as well ль intT<i-Sub]£?ct var iabi l i tés have been observed in a l l гк-rph' 1> gical.ml physb'l- git.al parameters mv'lved m lung d'jsimetry. A dise in p. int is the лпаГ'midi!

structure ' f Hit- lung which LS highly asymmetric with rand.-mly varying linear diim-nsunis,n^hiiiij anales <md number ' f dirways. M^rphamotric data on the human Lung were analyzed

to define probability distr ibutions of airway diameters and lengths and to study corre-lations <inong these parameters. Experimental results o£ deposition studies with cylindricalglass tu)}cs, varying flow rate, part icle size, linear dimensions and branching angles con-

rmed the applicabili ty of published theoretical deposition equations for straight tubesand provided additional information on deposition at branching s i t e s . The random walk ofaerosoi part icles during inhalation and exhalation m such a random ^ir-/3y structure wasthen simulated by Monte Carlo methods yieldinq probability distr ibutions for the depositionfractions in various lung regions.

With tnis information ом random variations of deposition probabil i t ies and geometriclimensions and additional information of the same kind on clearance velocit ies and basalcel l depths, lung dose distr ibutions could be derived instead of single mean values. Allparameters in th i s stochastic compartment model are described by truncated lognormalfrequency distr ibutions yielding basal ce l l dose distr ibutions which can be approximatedin Host cases by lorjTiûrmal distr ibut ions. Thesti basal cel l dose distributions are ofprimary significance for the definition of upper limits in radiation protection regulatuand for the correct interpretation of epidemiological data on lung cancer incidence.

DLVis ion of BiophysicsUniversity of Salzburg

Erzabt-Klotz-Strtisse 11A-50:o SdLzburq, AUSTR1Л

ASSOCIATED ORGANIZATIONS

Contra! Research Institute for Physics, Budapest,Hungary

Austrian Academy of SciencesHungarian Academy of Sciences

PROGRAMME

FROM 1 ' . 8 1

TO " / "

PnOJCCT - RESEARCH IN PROGRESS -

I UNLIMITED P1STP.1DUOUOMITTCD ГОП nUQLIOATION

DESCRIPTORS OR SE

lima dosimetryinternal conta:radon,model Li ng,dc-rx^sit ion

Hofmann, W.: Dosimetric concepts for inhaled radon decay products in the human lung.Proc. Spec. Workshop "Current Concepts in Lung Dosimetry", Sal t Lake Ci ty , USA.PWL-SA-llO'iy 11У83) :J7-43. Abstract in : Radiation Research <JI (1932) : ЗЬ6.

AUSTRIA IAEA/HPRA/IMo.11

Animal lung cios ime try f -r r.i : r, i n.-ih

F. DASCHIL, W.

I ABSTRACTOui present kiiowlcdgt- of bi it"ii-:al yf f fcts .иы d by mririlfd rude n Je.-tiy : г ' и " к " з i*trie human lung is Irirnuly based on experiments with 'Ufi-pront animal E i v c i t s . Althí.igmany biologif J l r e a r t m n s are : 1.1I1 t a t ive ly similar m a var ie ty of namnals, Ооы анЧгr e s u l t s which depen 1 pr imari ly on morpnological .IIKÎ physiological raramotnrs с in v.iryq u a n t i t a t i v e l y over <i largo range.

( NAME ANO MAILING ADDRESS O* ORGA


Erzabt-Klotz-Strrisse ÍI/•L-SO2O Salzburg, AUSTRIA

9 DURATION OfPROGRAMME

FROM ' F51

TO 12.0

nnOJCGT RESEARCH IN PROGRESSF^fVriAL 0П r iNAL ПСРОПТ WITH t>M0П UNLIWTCDOlGTniDUTION—R€f^

internal contamination,natur.il rad Latiori

radon,mudclUnn.

11h i i , F. and Hofmann, W. : The rt? 1 pvanct» of aniradl models for radionuclidc inhabit irj.an. Proc. Spec. Workshop "Current Concepts in Lung Dosimetry", i :al t Lake City, PSA

1ЪPNL-SA-UO-l^ (19Bi) :05-!O2. Abstract in : Rad. Ro=;. 'J1 (1982) :1

AUSTRIA IAEA/HPRA/No.11 AUSTRIA IAEA/HPRA/No.11

Microdosimetric analysis of radiation offrit s in Luna t issm

by inhaled alpha-eraittors.

"а ЖЛDosiraetry.Assessment of Dos«

to Man ( internal) .

3 AUTHORS OR INVESTIGATORSW. HOFMANN

ABSTRACTAt the c e l l u l a r level the concept of absorbed dose loses i t s s igni f icance and has toreplaced by the corresponding raicrodosimetnc quant i ty , I . P . the " spec i f ic cnerqy".Specific energy d i s t r i b u t i o n s of alpha p a r t i c l e s in lunq c e l l s and celL nuclei arecaused by four sources of s t o c h a s t i c e f f e c t s : (I) randomness of miclido d i s t r i b u t i o n son airway surfaces, ranging from uniform to "hot snot" d i s t r i b u t i o n s , (2) b iologicalv a r i a b i l i t y of t i s sue and c e l l u l a r s t r u c t u r e in d i f fe rent lung renions, (3) s t a t i s t l ev a r i a t i o n s oi the number of col 1цMr h i t s and the r e s p e c t i v e c e l l u l a r chord lengths,and (4) random nature of d i s c r e t o energy-loss events in microscopic t a r a e t s .

The h'i^ïL approach of t h i s microdoíjime-tr í с ana I v s i s i s the supcrposi t ion of con~piJtor-generated alpha p a r t i r l e t racks onto mannified imaqes of randomly se lected t i s ssect ions of the rat lung with tho aid of an linane a n a l y s i s system. The measurement of

the number of c o l l s h i t , the m u l t i p l i c i t y of c e l l u l a r h i t s , and the spéc i f i e enorayd i s t r i b u t i o n in these c e l l s . Tnis information ur. h i t p robab i l i t y and spec i f i c energyd i smal ignant ly transformed ^.clls and tne i r suât îal d i s t r i b u t ions.

Th i ь 'Ï<Ï^ lulu 11 i с гопсс p t hii;ï boon cipr iJod to trh 1 inh;il3tior i nf soluble radon 'iccapro'.lnrt-ч ,IK well -is г>~ highly însoïuï le - 1 'P'iOj рлг1"- LC-jlatos. К- : t • i " fcfc-ti * -i 1Ï ec.ron th" appl icat ion uf these n i^ rodos ine t r i c copsidertit ions to tne tïsscssn"ierit '7f 1 нпп^ancer itu-idencc in mm.

Division of ÍUophysii-ч

Erzabt-Klotz-StraS \e IIA-"O2o Salzburg, AUSTRIA

TiQN OO'NG THE J

FROM l o f i i

TO •

PROJtGT RESEARCH IN PROGRESSP*flTHH 0П FINAL ПСГЮПТ WlT+ffctMtTCD0Й UNLIWlTES-BtSTfltftUTION—ПЕ-РО

6 DETiC^iPTOHSORKE^WO

nternal ( on Lam i na11<">

r,g cancer .

manr aria l y s i s ,

ion,: lt.tOP.iun.

Hi lint . ri.vi ron. К i": h'.-'i. I ' O i . ' i . i i n - i : 1 ,

Invest n a t i o n tjf unhap.ced radmnucl ide depositingat bronchia 1 bi furcations.

AHH:- sment ^t Dosofс Млл ( internal) .

3. AUTHORS OR INVESTIGATOHS

W. HOFMANti, T. MAPTONKi; '

. t ion wworicii'iits wert1 Cf indue Led with upper nviman г espira t<Lo assess the behaviour of inspired a e r o s o l s . The work focused upon cy.iar,s i t i o n of "hot spots" at airway branchinn s i t e s . Aerosol mass median л т(MMADÏ ranged from 1 .') to 10.С fim, and inspirator '/ flow r a t e s were IS, Vper minute. Most airway b i furca t ions -:ere locat ions of enhanced deposit ii

ry t r a c t m~>I t t i t i n q depdyn.ifflj f di-i, and <o l in with m.ixi

a t bif

-iiuum mininq an.i m i l l m a indus t rThe infliioncf1 of those i n i t i a l

sidence- t i tn" s a t airway bi лгк hin

mal iginiit transformât г л .

f 1П' iinq 'иль lrnr-ortfint impithe inhala t ion ot airborne

on -лп ï-i

;-t ; . '"h-

NAME AND MAH.IN-. ADDRESS Oc OR

Division uf HmpiiysicsUn i v*±r s 11 y i i" iîti 1 zturg

Er^.abt-KLotz-Strasse 11A-"iO2() Salzburn, AUSTRIA

7 ASSOC'i

Pa rk , N.C. , USA

8 SPON5OH1NG ORGANIZA

FROMTO

PROJCCT RESEARCH IN PROGRESSPARTIAL 0П f IHAL nEPOnTWITtl ЦМOR UNLtMITCOOlS^niO^TION—REP

AUSTRIA IAEA/HPRA/No.11 CANADA IAEA/HPRA/No.11

Л track structure appruarh to radiât ionat environment a\ dost1 level s.

2 ElflOAD HEADING

W. HOFMANN, R . KAT2+>

1. ДВ5ГПАСТIn most cases of radiation exposure of the general public, or o£ occupational exposureof the individual, man is exposed to low levels of ionizing radiations. We -чррак oflow doses when biological targets, such as cells or cell nuclei, aro traversed only r-ysliiyle charged particles and their associated delta rays, and where interaction can beneglected. Tho low dose problem thus reduces to one o£ understanding the structure ofa particle track for the observed biological end-point", e.g. radiation-inducedcarcinogenesis.

The simultaneous operation of coll killing and transformation, with similar pat-terns of response, suggests strongly that there is a LET window for cancer induction.At the lowest LET'S, tho probability for malignant transformation is negligible smal1-At the highest LET'S, the probability for survival is negligible small. The 3ointprobability is highest for fast alpha particles, thus r-moh^btzing the1 significance ofincorporated alpha-emitters in radiation protection.

Л track structure interpretation of epidewiological data on cancer incidencesuggests that tho linear extrapolation to low doses is invalid. This hypothesis thatcancor induction is a "many-hit" process was tested with thtj observed lung cancurfrequency in uranium miners caused by inhaled radon daughters. If we plot the OXCPSSlung cancer risk per working level month (WLM) vs. the cumulative ey.posure in WIM,thon the best fits wore obtained by a quadratic or cubic: dose response function,revealing that lung cancer induction by alpha particles is a two- or three-hitmechanism.


Erzabt-Klutz-Strassc 11Л-5О2О Salzburg, AUSTRIA

'University of Nebraska-Lincoln, HE, USA

8 SPOSSOfING OHGANPZAT|0N(S1

Max Kado Foundation and U.S. Department of Energy

9 OURATION ofРпосялмме

FROMTO ТГГ —

РП(ЦССТ - RESEARCH IN PROGRESS -PAfffîAL-ОП FtNAL REPeHT-WW-t-fctMH

SUBMITTED r-on pu


dositnetry,limg cancer,risk assessment,track structure,epidemiology,internai contamination,natural radiationenvironment

W. and K a t ü , R._donos. Proc . Elth Syir.p. "<n Hier >tî isitiiotry, . lul ich, FHG, \Г)Ъ2. C.mri.Commun., Rep. EUR flW (1073) :^Л-Г_»73.

Development of Germanium Detectors for In-Vivo Measurementsof Low-Energy Gamma Emitters Studies of internal

contamination of Hunans


С. Ротпгоу, L. Noel

The current routine j_n_ v_W() measurement of low energy gamma emitters, such asPlutonium and uranium, is accomplished by means of phoswich detectors.

Several laboratories are investigating the application of germanium detectors forthis purpose, and the Radiation Protection Bureau is among them. An array ofhyperpure germarium detectors is being designed and constructed in cooperationwith a leadinn Canadian manufacturer.

The1 effects of the following factors wil l be evaluated:

1. Low background materials for detector housing.2. Specially designed detector shielding.3. Sophisticated signal processing.

The inclusion of these factors in the design, together with the inherent superiorresolution of germanium detectors, should lead to a significant improvement insensitivity.

Radiation Protection BureauBrookfield RoadOttawa, OntarioK1A ICI

Fном 11 82то

PROJECT BfSEARCH-lftLEHOGRESS- -

Uranium, Thorax» Germaniumdetectors in-vivo measure-ment

CANADA IAEA/HPRA/No.11 FINLAND IAEA/HPRA/No.11

Notional Uranium Tissue RegistryStudies of internalcontamination of humans

H. ['enley, C. Pomroy

The Canadian National Uranium Tissue Registry program was established in 1981 by theRadiation Protection Bureau, Department "Г National Health and Welfare. Registrantenrollment is expected to begin in 1933. The NUTR program is the first Canadian systematiiattempt to contact and gain assistance of workers occupationally exposed to uraniun and toseek and study uranium deposition in human tissue.

The objectives of the NUTR program are to:

Î . determine the distribution and concentration of uranium in the tissuesof occupationally exposed workers;

2. compare bioassay measurements of exposed individuals with the results ofanalyses of tissues obtained at autopsy; and

3. seek evidence of histopathologic changes related to any uranium depositionthat may be present

Workers in uraniun-handiing facilities will he enrolled in the program through thecooperative efforts of the NuTR staff and the medica?, industrial relations and healthphysics personnel of the facilities.

Potentia) populations for study will be quite varied because of occupational exposureto differen chemical forms of uranium, different levels and times of exposure, varyingability to identify populations exposed in the past, and the general interest and coopérâtiveness of the populations.

Radiation Protection BureaBrookfield RoadOttawa, OntarioК1Л ICI

FROM 3 81TO

Urani uninternal ContaminationAutopsyOccupational Exposure

Accumulation of fcJIodine in the thyroid nlands ofsubjects working in tracer industry

Studies ofradiation dosesm human thvmit

I I I - l

ijlonilb

Kalovi Kivinntty, Pirjo Nasnian, Juham Lepnaluoto

We measured the radioactivity of the thyroid glands of neoDle vjorkin>[ with4 да5тнАст j ^25r because iodine evarxxrates easily and may thereafter be conveyed via

the respiratory tract ir'zo the body and thus, into the thvroid gland of the nerson handlinni t . The measurements were made with a Nal (Tl) scintil lation counter, which had a colli-mator for thyroid measurements and the spectra were displayed by a multichannel analyzer.The equipment was calibrated by preparing a naraffin thyroid phantom in which an I 125solution was used. Measurements were taken on five different groups of laboratory workers:Group I (3 persons) consisted of people performing iodinations in industrial RIA nroductionthey handled iodine weekly using I 125 act iv i t ies of 5-10 mCi per iodination. Groun IT (6)was comprised of subjects who oerform monthly iodinations in a medical research laboratory,using I 125 with activit ies normaLly of 0.5-1.0 nCi per xodination. Group III (20) includedpeople who were responsible for different tasks in RIA research, but did not nerform ic*3-inations. Group IV (10) was working in isotope laboratories, but not handlinc I 125-label-led substances. Group V (3) was a control qroup.The means (in pCi) of measured thyroid act iv i t ies for grouns I-V were 74 + 40, 14 + 10,3 í 3, 3 + 2, 0.8 + 0.6 respectively. The calculated thyroid doses (rem/aT using the .41 Pi)narmniet No 11 were 1.95 + Q.Ob, 0.37, 0.08, 0.08, 0.02 respectivclv. The thyroid activityin the calculations was assumed to retiain constant during a year. This values shows thattne subjects using large quantities of radioa.ctivj.tv in íoduiations have notablv higherradioactivity values than the others. The maximum permitted annulai thyroid dose of 50 rei'1(ICRP 79) was not exeeded, but since however, the same DeoDle nerform iodinations for yearsi t is innortant to evaluate the working habits and conditions for handling radioactivesubstances.

University of OuluDepartment of Radiotheraov and Physiologv90220 OULU 22Finland

„.. . ,

t ROM 9 31"O

10 s'ATt ot AuvANcewtM

Reoaeor RESEARCH IN PROGRESSРл^КдаЗБШЮЯСШШКШШКЫШХЙСЖНЖХИСКЕНХЖХНЮХКЮв: REPORTSUBMITTED FOR PUBLICATION

Kadioiodinc'Itivroid glanclsAccumulationRadiation dose

HUNGARY IAEA/HPRA/No.11

Ti rU t AND SUIITITLÊ

C v l o K f i n - t i i e f f e t t b o f i n h a l a t i o n o î a i r Hadiat ionh x t e r n n l and I n t e r n a lCoiH.iminat ionHuman Г i t . . . I I 1 - 1

3 A u t H O R S o R i N v E S T i G A r o H S A l i i i . i s s v , Z S . , K . i n v . i r , В . , K o u - l e s , С I . , H . i n k , .!. , K r o m m e r , I . ,Sous, К.

I'lider t h e complex t i m d i t i o n s of underground o r e - m i n e r s exposed t o r idon-

d a u g h t e r s , chromosom.i 1 a h e r r a t ionh could be Г mini! in a f requencv ot s e v e r a I t imes

hi plier tít.tn in unexpo.seif pu pu I,it i on . S t a t i . s t i c a i ana 1 v s i s s i ; ^ ; e s t s к<ч*<1 cor re Lit i<

oi <IU e n t r i e s and r i n ^ s wit l i t h e c u m u l a t i v e e x p o s u r e s a s w e l l a s w i t h t h e annual

.iver.i^o e x p o s u r e , but not i n t h e c a s e s oi o t h e r ch гпщокоте от с h roma t i d t v p e s of

.ibvrr*nlmm. Thu pt«rren t j g f of p e r s o n s arrviitg tliientric /im) r i n s a b e r r a t i on s i s

Lm-reaKlnp w i t h c u m u l a t i v e a s wel l .is w i t h annual a v e r a g e e x p o s u r e . Our t ' . ita

p r o v i d e t h e f Í r s t b i o l o g i c a l e v i d e n t e t h a t an mnu.il e x p o s u r e i round or be low

Ъ Wl.M recommended bv t h e 1CRP as t h e a n n u a l l i m i t oi e x p o s u r e does not c t u ^ e

d e t e c t a b l e i n c r e a s e of c y t o p e n e t i c a l t e r a t i o n s when t u m p a r e d to " u n c x p o s e d "

p o p u l a t i o n . f u r t h e r r e s e a r c h i s performed t o t l n r i f v t h e e x t e n t of c o n t r i b u t i o n s

of Rn-dauKli ters , e x t e r n a l i r r a d i a t i o n or p o s s i b l v o t h e r a g e n t s to chromosomn1

. i b c r r a t i o n s .

5 NA\*t AND MAILING ADDHE55 OP ORGANIZATION DOING THE ЛОЖ

" F r é d é r i c J o l i u t - C u r l e " N a t i o n a l R e s e a r c h I n s t i t u t e f()

K a d i o b l o l o ^ y -ind R a d i o h v ^ i e n e11-1775 f iu t i apes t , COB. 101

ASSOCIATED OBGANI2ATIONIS'

Mecsek Ore-Mining Company, 1'ссч, Hunj-.a

8 4PONSÛHING QnGANi2AT>OMS>

IЛКЛ

Mitilbtrv ot Health, Hungary

9 DUHATION OfPROGRAMME

10SSBOU£Ct - RESEARCH IN PROGRESS -

б DESCftlPTOHS O« KE* WORDS

BIoloi-ícíil rndntlon ef fee t

Inhaled radon-datiKhterh

Chromosomn I abcrr.'U 1011ч

Human Ivmphoivies

K o t e l e S . C . J . : Problems of r.ulîohy>>f une in uranium m i n e r s . Proc . 2nd Conf. 0. cupat i on. ! 1i 'hysiLians", 198'J, i 'écsK o ' t e l e s . G . J . : IiLulni;lc.il t e c h n i q u e s in assessmen t of r a d i a t i o n bu rden ; F i r s t Panelon Occupai iunal and Envi ronmenta l Rebi-an-b In Uranium P r o d u c t i o n in Can.-id.i, 1981^ " J J J ^ ' - J ^ I ' - ^ . H ' U J / L L ^ B.»ill.»tlon Hazards in "l ininsK, ! / o t ó p t e c h n l k a , 26 , 1 7 2 - 1 / 9 . 19H3


Distribution of Thorium ID Human Tissues Effect of RadiationBxternal and InternalContaaination'£uman Data

Sunta С.И., Dang H.S. and Jaiawal D.D.

The monaiite aiaing and processing industry employa a siieable workforce who areoccupationally exposed to thorium and its daughter products. 1 programme has beeninitiated to assess 2*^ fn burden among the populations in the monasite bearingareas of South Vest Coast of India.

As the firat atept the distribution of thorium in tissues and body fluids ofsubjects from noraal background areas has been obtained. The analysis ie carried outby neutron activation technique with a minimum detection limit of 0.02 ng. The median„horium ( " ч ъ ) concentrations lag/g) in different human tissues »ltb rangea glna inparenthesis are: lymphnodei 64.7 (31.4-85.5), lungs" 9.2 (1.5-16.0), kidney! 1.7(0.9-4.0), liTerl 0.9 (0.2-4.9). hairi 4.9 (3.4-7.8), bloodl 0.011 (0.008-0.030) andurinei 0.19. UBS Orchard Leaves was used as standard reference material. Our »alm«for thorium concentrationi 70.4±10.8 ng/g, agreed well with the certified value64*7 ng/g.

The etudy is being extended to the assessment of the intakes and tissue burdenaof other isotopes. In particular, excretory tiasues and body fluids will be utilisedto examine the burdan io occupational workera and inhabitanta of high backgroundregions.

Health Physics DÍVÍBÍOD,Bhabha Atomic Research Centre.ВоыЬау - 400 085

Bhabha Atomic Research Centre

I'ROMTO 1984

PROJECT ПГНСЛПСИ 'N PRnfiRFSSPAnTIAL 0П riMAL ПСРОПТ WITH bWff fceОЯ-У«4.|М1Тев DISTRIBUTION^ REPOftTSUBMlTTSDFOfHHJBLICATION

6 O£Si

Thorium Human TissueInternal ContaminationVonazlte areasOcompational lorkeraTieauesHigh background areaa

00о


1. flTAf IT SOUS-TITHE

"Influence of iodine on the biological effectiveness of photon

radiation"

2 KUDrMOuEGtKERALt]

Kvaluation of dosj-^- *

3. AUTEURS OU СИЕПСМЕиМ

M. Coppola, G. Bertoncello, V. Capuano, M. Quintiliani, N. Vulpi

4. n:sjwc

Biological damage from exposure to photon radiation can be enhanced in the presence of

iodinated compounds, such as frequently used as contrast media in diagnostic radiography.

The influence of Na-iothalamate (IT-Na) «as first investigated on the survival of V-79

Chinese hamster cells irradiated in vitro with X- and gamma-rays, in a collaboration uith

the italian NRC. The results obtained using a 0.1 M solution of IT-Na indicate that at

exposures louer than 500 R the presence of the iodinated agent produces a marked increase

of the effect of radiation in the case of X-rays, but not of »°Co gamma-rays, altnough

some indication of an increasing effectiveness is obtained also for the latter radiation

at higher exposure. Calculations of the absorbed doses actually imparted to the cells

lead to the idea that variations of energy absorption due to iodine are able to account

for the change of radiation effectiveness at low photon exposure levels.

These results and the fact that an increasing rate of chromosomal aberrations uas

clinically observed in patients irradiated in the presence o£ iodinated contrast mediahave stimualated further studies in this area, in particular on the observation ofaberration frequencies in X-rays irradiated and unirradiated lymphocytes of fresh humanblood uith and without addition of IT-Na. The analysis of results as «ell as additionalexperimental tests are presently under way.

5. NOM ET ACES TRAV

ENEA ,• Dosimetry and Biophysics Laboratory, C.R.E. CasacciaP.O.B. 2400 - 00100 Roma, Italy

7. ETA

C.N.R.P. le Aldo Moro

Roma, I t a l y

8. 5OURCE161 OC FINANCEMENT

ENEA

ос ;..1Ш.

A • _ J

10. I- RfC^f^CHE £N CO'JIS -

R£PÍJO4T PARTIEL t^!TSZr."^3 ADIFFUSION CrîSœSSÎ iLLl'/ITCE -RAPPOÍ-T :UUr."S POUR Г'. 31ICATI0N

V-7Í. c e l l l i nLymphocytes

1. PEFtnEííCFS ОЕГ-rUBLICATIONi 4ECENTÍ5 DU UAUORA-OIHE t-e'JS LE MCME OO.MA1HE. . T ,

C. Barile, G. Bertoncello, V. Capuano, M. Coppola, Я. quintiliani - In: Microdosimetry.

Proceed, of the Eighth Symp., pp. 659-669. EUR 8395, Luxembourg 1983.

V. Capuano, M. Coppola, M. Quintiliani - Proceed, of the Third Conference on Oxygen

radicals in Chemistry and Biology. GSF, Neuherberg, July 10-15, 1983 (in press).


Л 11] low-up study nS perzo-.s who had received

:or thyroid disease cia/tr.03is.

2. RUBmouEGt-чЕП

I-:f.or:.al

cor. Lami'.atio

:!uma:. data.

ПГ-1

P. Al invista,!,:. .elvi3i,;.'..::astorina,L.üolor.oo,L.3onte,M.i;i Paola, ?. i'or.tana,

P.b.ctalli ,A. Peruasia ar.d j.Puncelll.

A sample of aJOUt _;,Ь00 people have beer. c.-iosen from a /rroup of 10,00"- peo-

ple exposed to 131 I for medical purposes during the period Iron January

}[!?6 to Lecemoer 1956. '.Ve have excluded all r.eoplastic pathology zr.d chose

patients who had received therapeutic dose levels of lji 1,

Individual estimates of the dose equivalent to thyroid have oeen ojtal-

:.ed and t::e health status oi" Tjne entire sample is oeir.g investigated at

present, Operative criteria for the cli..ical follow-up, including medical

examinât ions, are .icn.r. "et up,as well as the methodolof-y for the identifi-

cation ar.d definition of control samples.

P.O.. . 2-, Italy

- .tadiolOf^ Ir.3t. oi' Г'-ivcr.:ity, ;.ilar.o

- ";spfidale d i Jircoln, '. areoe

- Js pedal с c i " i r e o l o , list о krvi z±o

0£ ..J /.AU?.DIFFUVOMRAPPORT

C l ^ s a ^ ^ S ILLl'.'irCE -

- Internal irradiatio".

- Thyroid

JAPAN IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

Plutonium and Strontium-90 in the human body in the Japanese! Studies on <General Population and their Dosimetry I internal exposure

in man and dosimetry

Kauamura, H., Tanaka, G. and Shiraishi, K,

Transfer of radionuclides from the environment to man and estimation ofinternal dose have been matters of major concern with reapect to the effects offallout to humans released by the atmospheric weapons testing, and is of increasingimportance in view of the steadily developing nuclear power production and industriaactivities related to nuclear fuel cycles.

In this study, data on the distribution of plutonium in human tissues andstrontium-90 in bone in the Japanese are being measured to establish the baselinelevels of these nuclides in the human body and to review the data with respect tometabolic and dosimi>tric models, such as ICRP's. Emphasis is put on thedistribution of fallout plutonium in skeleton» or between trabecular and corticalbones, which is needed in extrapolating and analytical data for bone to the skeletalburden, and transfer factor for strontium-90 in the diet to bone in relation to apossible influence of larger content of stable strontium in the Japanese diet on thebasis of unit calcium content than that in the Western nations.

National Institute of Radiological SciencesLaboratory for Radioecology3609 Isozaki, Nakaminato, Tbaraki 311-12Japan

PlutoniumStrontium-90Human tissuesHuman boneDosimetric modelAnalysisSkeletonBaseline level

Japan Science and Technology Agency

-ÀQM ..{..тс- ./ .

H. Kawamura and G. Tanaka: Actinides Concentrations in Human Tissues, Health Phys.

Supplement No. 1, pp. 451-456(1983).

00

1 TITLE A N D S U B T I T L E

Dosimetric and experimental studies onlung-tumour induction by inhalation of radon

2 HROAD HEADING

Effects ofradiation

111


Hogeweg, B. and B a r e n d s e n , G.W.

4 AB5TRACT

The program is a combined theoretical and e^periffirntal study on tbeevaluation of the potential risk for lung-cancer induction in residents fromradon inhalation.

In the experimental part, WAG/Rij rats are exposed for about 18 months to arelatively low concentration of radon-daughter products. The lungs of theserats wi l l be examined for lung tumours, appearing after" a latency period as aresult of the exposure to the high LET alpha particles emitted by the radon-daughters.

The theoretical part involves the calculations of the energy deposition ofalpha particles in the various lungstructures in relation to biological andphysical parameters. These calculations are of interest for the extrapolationof lung tumour data in rat to man.

5 NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

Radiobiological Institute TNOP.O. Box 58152280 HV RijswijkThe Netherlands

SSOC А О G N12 TIONISl

8 SPONSORING OHGANIZATÏON1S

Euratom


FR0M:J9Ô0T o Í9Ô5

WMMMU - RESEARCH IN PROGRESS -

шкытвд ÏXXKRWB к ижкш.

RadonLung-tumor riskAnimalaîpha dosimetry

00К) NETHERLANDS IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

riTLE AND SUBTITLE

Evaluation of the biological effectiveness of various typesof radiation for different types of damages in culturedmammalian ce l l s .

I l lRelative Biologi-cal Effectiveness for celltransformation and chromosome damage


Barendsen, G.W. and Zoetellcf J-

4. ABSTRACT

Studies are carried out to obtain dose-effect relations for in vitro cell

transformation, chromosome aberrations and cell lethality induced by fast

neutrons of different energies and photons. These data are used to derive the

Relative Biological Effectiveness of these radiations and to determine the

effectiveness at low doses for different endpoints in various cell types.

Characteristics of these dose-effect relations will be applied to analyze the

effects of radiations in tissues with respect to late damage, in particular

cancer induction and impairment of tissue functions in dependence on the

dose.

On the basis of insights obtained from these studies, risks of low doses of

ionizing radiations for different effects will be evaluated.

Radiobiological Institute TNO

P.O. Box 5815

2280 HV Rijswijk

The Netherlands



a. Organisation for Applied Scientific Research TNO

b. Euratom

Э оиялтюм OPPHOGHAMME

T ° : -1-2-Í987

tO. STATE O:- ADVANCEMENTnnfiWCCT - RESEARCH IN PROGRESS -PAnTlAL 0П riWAL ПСРОПТ WITII LIMITEDOR UNLIMITED DIQTniOUTION- ПСРОПТCUOMITTCD ГОП PUBLICATION

6. DESCRIPTORS OR KEv

cancer inductioncellular effectstransformationchromosomes

Zoetelief, J . and Barendsen, G.W. Dose-effect relationships for induction of cellinactivation and asymmetrical chromosome exchanges in three cell lines by photonsand neutrons of different energy. Int.J.Radiât.Biol., 1983, vol. 43, no. 4, 349-362.

Mammary carcinogenesis in different rat strains after singleand fractionated irradiations with X-rays and fast neutrons

2 BROAD НЁА01Л

mammarycarcinogenesis,risk of low doses

J,J. Broerse, L.A. Hennen and M.J. van Zwieten

ABSTRACT Revised dose estimates for the population at Hiroshima and Nagasaki donot allow a reliable assessment for the risk of tumour induction after neutron ir-radiation. In consequence, there is a strong need for experimental studies onneutron carcinogenesis. Studies on radiation induced тагпгпэгу cancer in differentrat strains (Sprague Dawley, Wistar WAG/Rij and Brown Norway) have been per-formed for single and fractionated irradiations with X-rays and monoenergeticneutrons of three energies (0.5, 4 and 15 MeV). The aims of the program arethe investigation of the nature of the dose-effect relationships, the determinationof the relative biological effectiveness (RBE) of neutrons and the assessment ofa possible svnergism between irradiation and hormone administration. The eluci-dation of basic mechanisms of breast cancer induction are importent for risk-benefit analyses of mammography procedures. Histological analysis of tumours hasbeen completed and dose-effect relations are available for the induction of benignand malignant lesions, separately. The dose-effect relationships derived for thetwo classes of tumours in the different rat strains show considerable differencesin shape. For the induction of carcinomas in WAG/Rij rats, linear dose-effect re-lations have been observed after irradiation with X-rays and 0.5 MeV neutronswhich implies a constant RBE at the different dose levels. The RBE values cal-culated from the present studies are lower in general than those observed byother groups for beams of comparable energy. In the continuation of the pro-gram, emphasis is placed on studies of the effects of fractionated irradiation withrelatively low doses of X-rays and 0.5 MeV neutrons.

5. NAME AND MAILING ADDRESS OP ORGANIZATION DOING TH

Radiobiological Institute TNOP.O. Box 58152280 HV RijswijkThe Netherlands

DESCR'PTOHS OR KEY WORDS

mammary carcinogenesis,different rat strains,relative biologicaleffectiveness.

7. ASSOCIATED OHGA


Dutch Praevention FundNetherlands Cancer FoundationCommission of the European Communities


FROM,TO

Wit1 Z/iJ

10«T ~ RESEARCH IN PROGRESS -

J.J. Broerse. L.A. Hennen, M.J. van Zwieten and C F . Hollander. Mammarycarcinogenesis in different rat strains after single and fractionated irradiations.In: Neutron Carcinogenesis (ed. J.J. Broerse and G.W. Cerber), Luxembourg,Commission of the European Communities, EUR 808Й, pp. 155-168 (1982)

NETHERLANDS IAEA/HPRA/No.11 POLAND IÂEA/rîPe.A/No.11

oo


Absorbed dose due to mammography in various Dutchhospitals

2 BROAD HEADING

Doses due to X-raydiagnosis


C. Zuur, J. Zoetelief and J.J. Broerse

4 ABSTRACT l n m o s t o i t h e hospitals in The Netherlands mammography is performedonly upon medical indication. The mammography procedures in 14 hospitals havebeen compared with respect to the dose and dose-distribution in an acrylic plas-tic phantom simulating the breast. Dosimetry was performed with a Baldwin-Far~mer lonization chamber (BF-IC) and thermolumincescent dosimeters. Measurementswere made under conditions similar to those in routine mammography using theautomatic phototimers. A total of 23.000 women is examined in these hospitals peryear with an average of about two radiographs per breast. The diagnostic imagequality was determined by the use of a RA1I Mammographie Random Phantom, Thedose received per mammoradiograph as derived from the ionization chamberdiffered greatly among the various hospitals: between 2 and 21 rnGy for the en-trance dose, 0.1 and 0.3 mCy for the exit dose and 0.8 and 4 mCy for the meantissue dose. The mean absorbed dose in the breast per investigation varies from2 to 9 mCy. No correlation was found between the score of the image quality andthe mean absorbed dose. A comparison of the two dosimetry methods revealedthat the doses derived from TLD were considerable lower than those from theBF-IC. The mean ratios of the absorbed dose values (TLD/BF-IC) determined onthe surface and at 5, 24.5 and 19 mm depth in the phantom were equal to 0.6,0.85, 0.80 and 0.75, respectively.

In the continuation of the project emphasis is placed on determination of thedose distribution in the breast tissue. The dose distribution will be correlatedwith the location of specific target cells with the aim of assessing the risk for

Dr. J.J. Broerse,Radiobiological Institute TNO151, Lange Kleiweg2288 CJ Rijswijk, The Netherlands


8. SPONSORING ORGANIZATIONS]

FROM:Ql/82TO: 0.9 /95


f i . DESCRIPTORS OR KEY WORDS

absorbed dose,dose distribution,mammography.

1 1 . REFERENCES OF RECENT PUBLICATIONS IN SAME F1ÇLO ISSUED FROM THIS LABORATORY

L.B. Beentjes and J.J. Broerse (1981). Doses from Diagnostic Radiology in theNetherlands. In: Proc. Seminar Patient Exposure to Radiation in Medical X-rayDiagnosis. EUR 7438, pp. 87-100, Comm. of the Europ. Communities,Luxembourg,

Investigations of atv.os-jheric a i r pollution withgamna radioactive elements fron nuclear explosionsby means of çsizaa spectro.^etry .

External _and internalcontamination.

III-l

Jan Jagielak, Andrzej Pawlak, Andrzej Pietruszev/cki

4. A*ST«*CT

Gama spectro^etry i s applied on routine basis for radioactive a i rpollution measurementsл Dust samples are collected at sampling s i teat Warsaw. Concentrations of I-fa-54, 3e-7, Zr-95, Ru-103, Ru-106f Sb-125,1-151» CG-137, Ba-140, Ce-141, Ce-144» U-nat and Th-nat are determined.Special equipment for low-level gamna measurements i s constructed inCLOR. The hazard to the population and to the environment caused bythe a r t i f i c i a l radioactive elements in atmospheric a i r has been estima-ted as usually foreach following year*

S. NAME AND M A I U M G AOÎJAESS Of O«GA»«ATIDN OOlHC TWC wpKK

Central Laboratory for rîadi>-.lo-;ical Protection

IConwnliowa 7, 03-194 '-Varsav/ , Poland

D 0*CJ.N1ZATIOH(SI

Polish Atonic Energy Agency

T O : . . / - •

measure-ments, i а ь в

Garuria radioactiveelements in a i rat V/arsaw*

Air pollution.Dose equlTBleat.

CI.OR reports


2. Studies of Internal Contamination in Animals

85

00


Eficácia de un plan terapêutico descontaminante pararadionucle idos no transportables incorporados porvÎ3 ínhalatoria

2 ТЕМА GENERAL

Estúdio decontaminacíón

ж-г

Gomez Parada I . , Fernandez Oegîorgï С , Dubner D.L.

RESUMEN

Se analiza la e f icác ia de d is t in tos planes terapêuticos descontaminantes paraîncorporaciones de radionuclefdos no transportables por v 'a inhalatorîa.

El esquema experimental consiste en la contamiпаеión de ratasCe-lM y la aplicación de dos acciones descontamïnantes: 1. aplicación dede DTPA-Ca-Na 3 por inyecciÕn ïntraper j toneai , y 2. apl icación de dos dnsiCa-Na -i рог vîa intraperi toneal .

Se évalua la ef icác ia de los tratamientos en base a la comparaison de la car-ga máxima en hTqado y hueso, la fraccïôn de la caraa pulmonar transferida en híqadoy de las relaciones entre excreciôn fecal y ur inar ia .

ar conuna dos is

is de DTPA-

Comisiõn Nacional de EnergTa AtômicaGerencia de Proteccíõn Radfolóqfca y SegurtdadAvenida dei Libertador 8250Buenos Aires - Argentina

ORGANIZAOON V QHGAN12ACIONES PATROCINADORAS

t 13827 , 1983

10. S.TUACION

RHOWXXKX-INFORME PARCI

6. DESCRIPTOHES О PALABRAS CLÛ

De s con t am Î na n te sCerîoContamiпас iõn i nternaAnî-nalesAe 3 о 1 e s


l ' iot Stud> im Radiât ion ! vpnsurt,- ,md I.uny; C,mi-LT MortdliSpec t n of Mmtrs

A 11 f -_'in te rna l andInternal ( tMit.unin.ii ivn.

W1CLE, D . Ï . ; MURRlSdX, H.; STuCKKR, H.

Л j i i lot study i s bo шц performed со absess tlio r isk uf lunp cdnctT from i-xposiirc lu

radon ddtightcrs .шгоц.ц prt-vioij-sly exposod fLuor4i)iir workers in St . l,jwtt*m:ti

( Sowiound-

land. Tht? study c o n c e n t r a t e s un the radon daughter exposures, smoking ii i^corios .mJ

work h i s t o r i e s of tho fluorsj» ir workers. An ^stimato «f the excess 1ипц cancer

iiii- icienci.' and a r i sk index iur 1ипц с.пичг ль .i fimctLon of liiVtimt laJnn d.iunhter

cípusurt nr<,- t.'Xpt'1'ti'd lo bu dtTÎVL-d.

Department of Xati.on;il Health and Wei faLaboratory Centre for Disease ControlLCÜC Bui ld ing , Tunnuy's PastureOttawa, OntarioCm.ida K1A OL2 _ _ ^

S t a t i s t i c s CanadaAtomic FntirRv Control Btmnl

Atomii- Гпогду Control Bo.irdDupartnu-nt of National Health and WelfareSt.-iriHrics СаплНя

FROMTO

10RESEARCH (14 PROGRESS

exposurc-dosimetryepidemioliiRVminesuptakerad ia t ion protec t ionrridionucl ides

0000 FRANCE IAEA/HPRA/No.11

ETUDE DU TRANSFERT GASTROINTESTINAL DES TRANSURANIENS CHEZ

L£ SINGE. INFLUENCE DE LA FORME CHIMIQUE ET DU REGIME ALI -

MENTAIRE.

Etudes de la con-ftamination interne chezles animaux

Henri METIVIER, Daniel NOLIBE

La CIPR a élevé d'un facteur 300 le facteur de t rans fer t gastrointest inal du

neptunium f ] = 1.10"' en prenant e/i compte des expériences animales u t i l i s a n t des

grandes quantités de Neptunium 237 incompatibles avec l'environnement. En u t i l i san t

de plus fa ib les concentrations, à l 'a ide de l ' isotope 239 nous avons montré que le

coef f ic ient f j se s i t u a i t chez le singe au niveau de 1.10~3. Pour cet élément l ' i n -

fluence du régime al imentaire est relativement f a i b l e .

Les valeurs retenues par la CIPR pour le plutonium sont infér ieures aux valeurs

expérimentales, c 'est pourquoi nous débutons une étude du coef f ic ient f i chez l e - s i n -

ge après ingestion de plutonium à d i f fé rents états de valences. L' inf luence du régime

alimentaire et cel le de l 'âge seront également étudiées.

Le t ransfer t gastro intest inal de 1'Amèricium également présent dans les déchets

n fera l ' ob je t de la dernière part ie de l 'étude.

COMMISSARIAT A L'ENERGIE ATOMIQUE - Département de Protect ion Sani taire - Centre d'Etudes de Bruyères le Châtel -BP n" 1Z - 91680 Bruyères le Châtel - France

8 iCUfi:rf&l £>< firi>"CtuCNT

COMMISSARIAT A L'ENERGIE ATOMIQUE (CEA)

1. i

.ос.ШЗ; . .-1985

HE ENCO'JCS-

Actinides

Transfert gastrointestinal

Valences

Singe

Déchets i

Régime alimentaire

I) .4.. Ш.Ш.ЕЯ,. R.. MASSE». J-.UFUMa..Bad1opcotectian, 1983, 18,1, 13-17

2' ,H..Jf.UVJÍR,.R..WSS£,.J..LSF№№,.I!adiatioii.Risk Protection (congres IRPA) à paraître


* selon le cas

TTUDE METABOLIQUE D£S COMPLEXES DU PLUTONIUM SOLUBLES DANS

LES SOLVANTS ORGANIQUES. ESSAIS THERAPEUTIQUES ASSOCIES

Etudes de la con-

tamination interne chez

les animaux

Henri METIVIER, Daniel NOLIBE

Le complexe Pu-tributylphosphate (Pu-TBP), pierre angulaire du procédé de re t ra i -

tement PUREX présente che? le rat.et le. singe un devenir biologique intermédiaire en-

tre les formes nitrate et oxyde. La différence principale reside dans l ' ineff icaci té

du traitement par le DTPA, liée à la présence d'un complexe Pu-Transferrine plus sta-

ble que celui issu d'une contamination par le Pu-nitrate. Une recherche de nouveaux

agents de décontaminations est en cours (synthèse et essais thérapeutiques du LICAM C)

Une étude des composés analogues au Pu-TBP est nécessaire pour savoir si le devenir

biologique de ce complexe est unique ou représentatif d'une nouvelle classe de compo-

sés qu ' i l serait u t i le d'introduire dans la classification CIPR.

COMMISSARIAT A L'ENERGIE ATOMIQUE - Département de Protec-tion Sanitaire - Centre d'Etudes de Bruyères le Châtel -BP n° 12 - 91680 Bruyères le Châtel - France -

COMMISSION DES COMMUNAUTES EUROPEENNES (CCE)

COMMISSARIAT A L'ENERGIE ATOMIQUE (CEA)

.o t . 1.983«'••J.385

ХЯВМЕГ -RtCMS F.CME ENCOVJ4S-

шшюишшвихтхшнвсхтш-

Plutonium

Pu-TBP

Poumon

Contaminations

Animaux

Aérosols

Ret ra i tement

i: Н-Л.ЩУЯЯ.,. P...№SSE.,.J..LJFUH6..tleanb. Physics,. 1983, 44,6

2' H.-4E.T.I.V-I£«.,.«-:MASSE,.J..LA(;UllA,.Ra.(liAtip.n Research, 1982, 91 ABS, p 363

* selon le cas

INDIA IAEA/HPRA/No.11 ITALY IAEA/HPRA/No.11

Environmental Саша Radiation Monitoring using TLDs aroundatomic power stations at Tarapur and Rane Pratap Sagar

111-2

Effects of Radiation

Basu A.S., Sasidharan H., Kathuria S.P., Nambi K.S.Ï. and Sunta С.Ы.

The environments of the Atomic Power Station at Tarapur {TAPS, Maharashtra) andRena Pratap Sagar (RAPS, Rajasthan) upto radial distances of about 20 km have beencontinuously monitored for the background radiation levels using natural OaP, thermo-luainescent doeiaetere (TLDa). The monitoring hag been done un a quarterly basis atabout 12 locations each for nearly 12 years in the case of TAPS (pre and post opera-tional) and 5 years in the oua of RAPS (post operational only). The results of TAPSenvirons show clearly a biœodal distribution on a log-normal frequency plot. Anincrease or about 10 to 20 mR (2.58 to 5.16 uO kg"1) in the annual averages isobserved in locations within 2 km of the station over the preoperational level. Nosignificant increase in external radiation level due to RATS operations could bedelineated from the poet operational dato recorded at SAPS.

Health Physics Division,Bhabha Atomic Research, Bombay - 400 083,India

Bh&bha Atomic Research Centre

PfiOGRAMME

FROMTO 'continuing

10. STATE OPROJECT -PAflTlAL OR FINAL REPORT WITH LIMITEDGR-UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

Environmental SurveillanceAtomic Power Station,Tarapur, Rana Pratap Sagar,ТШ

Bull. Radn. Prot. (Bombay) 6 (2), 29-32 (1983)

Determination of the Leaching behavuir oi the ^03-Hg Carnauoa

Was Bonding. A penumotachographir Device tû 0n-Line Measure

Respiratory Patterns in Small Hoiients Studies of Internal

Contamination in Am

M.Calamosca, P.Bassi, P.G.Pagano, C.Lombard!, G.Forner

To gftt a better evaluation of the long term clearance in rats exposed to carnaúba wax

few.} aerosol,203-Hg has been choosen as a label, because of its radioactive behaviour

ind its leaching characteristics checked. In vitro measurements, carried out by means

show a leaching less than 10% at the end of•f both surfactant and Kanapi11y solutio

Mercury-c.-w. bonding seems to be weaker in vivo than in vitro. Parallely the group

is developping a new kind of on-1 me pneunu tachc^raphic device to record breathing

patterns during the inhalation phase. According to the first encouraging results, ef-

forts are now devoted to interface the transducers to an host computer in order to

store and automatically analyze the recorded date.

ENEA - Dipartimento PAS

Laboratório Física e Tossicoiogia degli Aerosol

Via Mazzini 2 - ДО136 BOLOGNA (Italy)

-Aerosol

-Leaching

-Clearance

-Pne umo tachograph

.1 " v , ' •; P. ,L.i' TION L_


1 T t i r f IT '-.Ouf. T,tr-E

A Exposure Chamber for Acute Inhalation Experiments with

Small Rodents

" Я-2.Studies of internal

contaminat 1 on in an 1 nab

H.Calamosca, V.Tadolim, G.Tarroni, M. [3. Belvisi , P.Bass:

A novel exposure chamber for acute inhalation of small mients has been dos i£r

built.

The chamber is of the fast filling type, thus avnidmg agglomeration Jnd unn«<

excess production of radioactively labeled or toxic particles.

The small size and the parallelepiped shape allow the chamber to he used under

tory hood. Animals are held in Lucite cylinders, /.here they stay .marines t he t

breath naturally through a hub provided for quick con

supply of aerosol is provided to each of a maximum of ,M

Tests with radioactivelo labeled aerosul, show goodhomogeneity of concentration.

ion to the chamber,ninais.

hara.-terist.ir of stahi!

labcra-

svd and

Л fresh

i t v arid

5. h>OM f A^'U'.vE ТОП/IE SI L'ETABLIS^'МГЧТ A

V AN1 Î PIT TCP

L ( S ~ P Л v •- • I *

EWEA - Dipartimento PAS

Laboratório Física e Tossicologia deli Aerosol

C.R.E. E.Clementel

Via Mazzini 2 - ДО138 BOLOGNA (Italy)

E N U

JI^IIKZEIMË

POLAND IAEA/HPRA/No.11

1. tiT.E AND SUirrTLI

Incorporation of Tritlated Water or Organically Bound

Tritium into Amloo Acids of braiu Proteins.

m - 2

Int*mal Contamination

in Animals

M. KowalsKs

The »im of the stuay was to examine tne tritium incorporation into Hino acid*

isolated Ггош tne Drain proteins of rats exposed lor tour generations to trit iatcd

water /37*0 lib q/ml / or to organically bound tritium /OBT/ in foud Л8.1 kBq/g /„

It was founu that after liJfe-tiae eipoiur* the specliic activity ot aonexchangi

able tritium /NET/ in anino acius of brain proioiaswaa higher after exposure tu

OB* than to tr it iateo water.

Central Laboratory for fiaaiological Protection

Konwaliowa 7

UJ-194 Warsaw, Poland

7. J-SSOCIATED om__.-.i£ATio>«si

- i tate Agency for Atomic Energy

S ou**-rio~o*FltOVnAUME

M«iEs__=-_WitUI. я£»св- WITH

82

E.

WITS»

OBGAKICAUY BOUND ТВШ1Ш

TBITIUU INCOKPOBATION

AMINO ACIDS

POLAND

Biological Iflect ol Tritium.Iftect •£ lilatlme intake uf organically oouixl tri t i eana trltiatod ««tor on the oocyto> ol rats.

Ш-22. B*0AO HEAÍIU

Studies of

Internal Contamination!

in Animals I

Z. Hetriuk-rlis, U. Wasllewska-Gonullca

Wiatar rate were exposed со coastanb activity of tritium in driOKlng aater or to

tritium organically bound in Xooil l'rom conception ol' *Vj generation through matu-

rity. Fomala offspring «ere killed at the age oi 21 and 71 days, ana the oocytea

in tholr OYariOg wero cuuntod. Btduction in the oocytv number in ttie ovaries of

fOB*l« cxposod to tritiatta rood » u Digger ihan in thu ovarlus of iomales expov

sad t* trltlattd watar, Tuo do.о rate dependence of the survival of small oocytes

•ad на exponential character. tBe damaging efiect ox tritium was tor thé pt-iod

from conceptloa to 21 Hays of **• bigger than troa 21 to 71 dujs ol' age. Of all

stages of oocytd development! the highest sensitivity ol tritium irradlatiun was-

obsertad in email eocytes and oouyte» aitn one complete layer of fulllclo cells.

Аз a rcsultf relativo number of the growing umJ large oocytes increased.

S. CAME «NDMMLIMC ACOKEtSO' СЯЕЯНСДТФН DOIMC ТмЕ WO*K

Central laboratory for ladlaiogicai Protection

Konwaliowa 7

03-194 Warsaw, roiasd

6- OtSCAIPTOej ОЯ ciT WDHDl

JÏIIIATED WATEB

0BGANICAL1Y BOUSD THIIIUM

BIOLOGICAL EFFECT

OOCYTE SURVIVAL

State Agency for Atomic energy

f*0M0.1/88тс Ofi/83 I SU8MITTED РОВ PUBLICATION

Z. Pletrzak-fli>i effects et cnronically ingested tritium on the oocytes oi two

generations ox rats. In: Developmental Iffoct* et Prenatal Irradiation. Eds H.

Kriogel at al. limiav Fiscner Variai atuttgart. Mew Yorsj 1482 op.


3. External Irradiation (Animal Studies and Human Data)

93

AUSTRIA IAEA/HPRA/No.11 FRANCE IAEA/HPRA/No.11

1 TITLE ANDSUBTITLE

Radiation-Induced changes of íntruCüLlular (Ussulved oxygen

2. BROAD HEADING

Effects ofradiation :III - :; and III - 3

THOnSOH INVESTIGATORSSteinhãusler F. , Heidegger W., Huber M. and wõrgõtter E.

An essential component for the maintenance of the cell metabolism is the supplyABSTRACT o f dissolved oxygen in the biological tissue. Several publications demonstrate

that irradiation o£ animals causes an uncoupling of oxidative phosphorylation. Furthermore,the relatively high concentration of uxygen in biological systems is known to influence con-siderably the follow-up reactions of water radicals. Hitherto the effects of radiation oienergy metabolism have studied mainiy on yefist and bacteria. From these results it is indi-cated that radiation-induced inhibition of respiration is delayed, the severity and extentof which are dose-dependent. This could result from the excess production of an inhibitorprotein that is normally present within the cell. However, relevant information for mamma-lian cells is scarce. In this study a two-step-approach is taken:

1. in vitro-experiments: human lung cells are irradiated with СобО gamma radiation andthe effect of radiation on cellulur respiration is stud .ed, using sealed, thermostati-

cally controlled microchambers and miniature pobrographic electrodes. In addition the

intracellular partial oxygen pressure ipO2) is determined in individual cells with

spe^i.-' qlciss micraelectrades (tip diameter: I - 3 /irai .

1. in vivo-exporlments: rats are exposed to either external gamma-radiation cr internal

alpha exposure. pO2~mcasurements are carried out with polarographic needle electrodes

(tip diameter: O.7 mm), determining the pO2-pressure in liver tissue.

The results from this study will provide further information on the basic inni. nanisms of

the action of radiation on cells, with potential practical implications in radiotherapy

of cancerous tumors, where the question of therapy success depends, e.g. on the problem

of '"reoJiygenatod" ecl 1 s.

Division of Biophysics, University of Salzburg

Erzabt-Klotz-StraGe 11

Л-5О2О Salzburg, Austria

ASSOCIATED ORGANIZATIONS)

Austrian National Bank

FROM- ?. > .u.1

то : IT.


6. DESCRIPTORS OR n£V WORD

oxygen,external irradiation,human cells, animal,liver, tissue

Steinhãusler, F. , Reubel, В. , Heidegger, W. , Huber, И. and Pohl-Ruling, J. :Low-Level radiation induced biophysical effects of mammalian cells. Book of Extended

Synopses Int. Synp. on the "Biological Effects of Low-Level Radiation with Special

Regard to the Stochastic and Hon-Stochastic Effects", Venice, Italy, 1983;

1. TIT"I IT IQUfcTl

Etude expérimentale chez ïe porc des irradiations

localisées à forte dose.Evolution suivie par thermographie microondes.

2. ftlltNIQt/l OINCNALI

IrradiationexterneExpérimentation animale"

F. DABURON, J.L. LEFAIX, J . REMY

Cette étude est développée dans le but de fournir une contributionexpérimentale à la recherche d'une doctrine thérapeutique dans le cas d ' i r râ -diations aiguës localisées chez l'homme.

L'emploi de méthodes non traumatisantes d'exploration de l ' intensitédes lésions nous a conduit à aner les recherches sur la thermographie localeet la biochimie systémique; les résultats de ces mesures - ajoutés aux étudeshistologiques rëaiiséesau moment des sacrifices réalisés à des temps différentsdoivent nous permettre d'évaluer l'importance et l'étendue des lésions, leurevolution dans le temps et l 'e f fe t des traitements pharmacologiques.

5. NOW ILIS T

Commissariat à l'Energie AtomiqueI.P.S.N. Département de Protection Sanitairelaboratoire de Radiobioîogie AppliquéeF 7Я2Б0 Jûuy-enrJosas _ _ _ _ ^ _ ^

9. #О1/ЛС#Ш Off ПНАнС*№ШЫТ

СЕЛ CEE BIO - С - 347 - 81 - F

oi. - 1980

*• •— 1984

•НЮ»Г - R£CH;fiÇM£ EM COURS -

RAPPORT EQUM'S ПОЦП РЦILLIMITEE -

в. Dlic*ir»tynj ou MOTS CLf j

- Irradiation externeForte dose localisée

_ Porc- Thermographie par

microonde- Histo-en^ymologie- Biochimie locale

et générale.

1:) .,..7.t.h..Lrit...c;angr.G^...Rad4.Rese.ir.qh1.AiDStecdaiu.3-8 july 1983 (Ref D3.06)

2)

3)

* selon l t cas

va FRANCE IAEA/HPRA/No.11

DETERMINATION DE L'ESR DES NEUTRONS DE FISSION POUR LE

CRITERE LCTALITE 50/30 CHEZ UN GRAND MAMMIFERE.

Irradiation

externed'animaux

3. AUTCVHS OUCMIACMIUM

Guy LEMAIRE, Jean MAAS, D . P . S . / G . H . R . / D . R . E . T .C E . A . / CEN-FAR B.P.n 6 92260 FONTENAY AUX ROSES

*. MSUUC

Des porcelets issus du croisement de premiere generation Large White x Land raceet pesant 16 à 20 kg sont soumis, par lots de douze et en irradiation unilatérale parle flanc gauche, à la fluence gamma du Cobalt 60 ou à des fluences mixtes neutron-gamma dont le rapport dose gamma/dose neutron peut être modifié.

Aux"mid-line tissue dose free in air"utilisées à ce jour ( 3 à 6 Gray), lesanimaux présentent la forme hëmatopoïétique du syndrome aigu de l ' irradiation et , entermes de mid-line tissue dose free in air, l'EBR paraît supérieur à 1 pour ce critère

Cependant, pour mieux parler d'EBR, i l sera nécessaire de tenir compte de ladistribution hétérogène des doses gamma et surtout neutron en les déterminant auniveau des différents territoires médullaires et d'évaluer alors la survie cellulairepour l'ensemble du tissu hëmatopoïétique.

. мои ет Aonesxi POST,

D.Г.S. / G H R CEA/ DRET

Centre d'Etudes Nucléaires de FONTEHAV AUX ROSES

B.P. n 6 92260 FONTENAY AUX ROSES (FRANCE)

D R E T

S. SOU"=(I&IOI '

CE.A. - D R E T

S. DUfttf OUVHQQItAUMf

Dt:.....03 / 19814 -.12 / 1986 ХЯШШЖКОДШХВШШШХШХ

Irradiation externe

E6R neutrons fissioi

Animaux

Letalité 50 / 30

1] . " t ' i n f K C I S O i l ' U H I C AYtOMt HtClNTCS CU bASOMATOlAf DANS L[

Note C E . A . - N - 2307 AOUT 19821) Л

2) Л &№# AM .S.emi.na.i.r.e. Леди. А .ЧЫЗДВД» Де. Двд/.0.7./1983sur i n v i t a t i o n du Dr, BROERSE ) Hemapoïetie syndrome in pigs.


Dose-effect relationship of chromosome aberrations of inviLro irradiated human peripheral lymphoevtes

2. BROAD HEADING 7|7"

Effects ofRadiation,

вьзExternal Irradiation,III-3


A1massy, 'IS., Kanyar, В., Koteles, G.J.

. ABSTRACT

In tiie framework of the IAEA's co-ordinated research on "Use of chromosome aberration

analysis in radiation protection" we deal with the determination of dose-effect

relationships of aberrations in human peripheral lumphocytes irradiated under

conditions agreed upon by the participants of the programme. The anta on

x-irradiated blood (£00 kV, 20 mA, 1 mm Cu filter, 37 C, SSD 60cm) were fitted to theequation Y = aD + bD by linear regression. The doses applied were 0.5, 1, 2, 3, and4 fïy. The number of metaphases were scored until 50-100 dicentrics were found. Thecoefficients aro as follows:

For dicentrifs:

for "total" aberrations:

a = 11.8 + 2.4 x 10

b » 5.22 + 0.69 x 10~

a = 36.6 + 4.3 x i0~2

b = 10.9 + 1.3 x 10"2

The observed data for dicentrics as well as forto the predicted ones.

'total" aberrnt ions correspond well

5. NUME ANO MAILING ADDRESS OF ORGANIZATION DOING THE WORK

"Frédéric Joliot-Curie" National Research Institute forRadiobiology and Radiohygiene

H-1775 BudapestРОВ. 101. Hungary

SPONSORING ORGANIZATIONS!

IAEA

Ministry of Health, Budapest, Hungary


FROM 07/ 82TO 12/ 85

" RESEARCH I N PROGRESS -

6 DESCRIPTORS ОН KEV WOROS

Biological radiation

effects

Chromosomal abei rations

x-irradiated lymphocytes

11 REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY f

Koteles, G.J., Bianco, A.: The need for and importance of biological Indicators o r

гШТаПап ettëçts~iïïtlTapecial reference to injuries in radiation accidents, IAEA-TECD0C-

Kubasova, T.: Availability and problems of biological27J, Vienna 198;

Koteles, C.J., Almissy, Zs. .indicators for radiation injury. Proc. XI. ReR. ConRr. Vienna 1983

* selon le cas

HUNGARY IAEA/HPRA/No.11 ITALY IAEA/HPRA/No.11

J

1. TITLE ANDSuaTlTLE

Use of Micronucleus Test in Detection of Radiation Effect

2. BROAD HEADING TTT - 0

Effects .if

Radial ion

External Irradiation,

ПГ-3.


Almássy, ZS., Ko te l e s , C.J.

ABSTRACT

Among biological indicators of radiation injury beside the chromosome

aberration analysis the micronucleus frequency in lymphocytes are investigated. Tlie

procedure involves several factors which point to the advantages as well as

disadvantages of the technique. To overcome some technical uncertainties in the

reliable recognition of mieronuclei we have introduced a fluorochrome staining, the

acridine orange and other modification to preserve the cytoplasm by moderation

hypotonization. The improved and modified technique results in an unequivocal

recognition of micronuclei. Preliminary data on in vitro x-irradiated human

peripheral lymphocytes cultured for 48, 72 and 96 hours suggest linear-quadratic

dose-effect relationships.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOIMG THE WORK

"Frédéric Jaltot-Curie" National Research Institutefor Radiobiology and RadiohygieneH-1775 Budapest, РОВ. 101Hungary


IAEA

Ministry of Health, Budapest, Hungary

FROM-.0X /81

TO: 12 /85

10. STATE OP ADVANCEMENTХНВДБХХ- RESEARCH IN PROGRESS -

Biological Indicators

Micronucleus test

Human lymphocytes

x-irradiation


Koteles, G.J., Almássy, Zs., Kubasova, T.: Availability and problems of biologicalindicators for radiation injury. Proc. XI. Reg. Congr. 1RPA, Vienna, 1983

1. TITPÏ Lf SOUS TllRt"Radiation effects of the eye-lens of the mouse"

2. HL'DnioUExt-Tnal

on (stan ima 1 s .irel ev.inl

r radi -

id resulto тли)

nt-3

M. Coppola, V,, liertoncf 1 lo , M. Di Paola

Among the non-stochastic effects of ionizing radiation the formation of opacififation

in the lens of the eye associated with external irradiation lias a prominent position.

The mechanism of induction is not untirelv understood, however it has to do with injure-

to single cells in the proliferating part of the lens epithe Experimental studies

on the mouse have especial advantages since

cells is by far shorter than in man and tr

be observed within a reasonably short time period. A

the time of turnover of these epithelial

ore the expression of radiation damage can

•* tema t i c study of radiationeffects on the eye-lens o{ i r radiated mice has therefore been conducted for sif i r s t considering the formation of point opacit ies following externat irradia

wide spectrumthe number of

of low- and high-LET radiation q u a l i t i e s . More recently, inveslills individually damaged was undertaken taking as an end poin

ral yearsion by л

д t ion

the

appearance of micronuclei. Tests are presently carried out using monocnergetineutrons as well as X- and gamma-rays. Modes of treatment include both acute and fraction^ated i r radia t ion. A preliminary analysis of available resul t s confirms high RBK valuesfor fast neutrons as already observed in the case of opacity formation.

ENEA, Dosimetry and Biophysics Laboratory, C.R.E. Casaccia

P.O.B. 2400 - 00100 Roma, Italy

л. J.9.7.7

ID. n"lO'AVA4'-ï"t»i

aie : U'-ION í^KE^i í ÍLLÍWI ГЕЕ

Пуе-lpnsMLcromiclei

M. Di I'aola, M. Coppola, .1. B a a r l i , M. Bianchi , A.H. Sul l ivan - Biological Responses t ovar ious neutron energ ies Erom 1 to 600 MeV, I I . Lens Opaci f icat lon in Mice. Kaciiat. Res.

84, 453 (1980).

í '

ITALY IAEA/HPRA/No.11 ITALY [AEA/HPRA/No.11

G. Doria, L. Adonni, A. Di Michèle, M. Caraviru , С. Mancini

Radiation damage and recovery of the immune system"

External irra-J Jf[ ~diation (studLes—

on animals and result

relevant to man)

It is well established that the immune system is not a simple array of

independent cells but is rather a complex network of interacting partículateand soluble elements. The antibody response is modulated by signals passedamong different types of cells that regulate the intensity and duration ofthe response after antigen-induced perturbât ion of the immune system. Sincehelper and suppressor T lymphocytes play a key role in immunoregulationtheir radiation damage is likely to impair surveillance mechanisms againstinfections and tumour appearance and development. Our radiobiologicalstudies on immunoregulatory T cells have been addressed to the radiosensi-tivity of antigen-specific suppressor cells induced in 20, 90, or 720 dayold mice a week before whole-body exposure to 50, 100, 200, 300, or 400 rad.The radiosensitivity of suppressor cells was found l0 fold higher in 720 daythan in 90 day old mice, in the latter group being 50 fold greater than in20 day old mice. This experimental approach will be further extended toexamine the increase in radiosensitivity of suppressor cells in old animalsin which alterations of T cell subpopulations have occurred and accumulatedwith advancing age.

fclNEA, Laboratory of Pathology, C.K.J-;. CasacciaP.O.B. 2Л00 - 00100 Копа, Italy

C . E . E ,

6. i

- Immune systein- Helper T colls- Suppressor T cells- External irradiation

O. S t - . " C f " . , ОГ

E.N-Е.Л.

0. n v p . t t a ' j * ! W * w « í

--... .J.. 83

10. E7*T O'fVA'i'.1 "JESTСГГТА - Г.ГГ'Ч -СмЕ ENCOJ^S-

D г ; v , ~ . \ х ' л ~ Х 7 . . - ' . ~ - : % • L i V i • £ = -

я/~:-с;HT : L 4 . ' " ' Г 1 ? ^ FJSI . .CATION

efforts of neutron г-хрочагс "

2. «..'cf-'a;. ; с >- n, .External i r r a d i -at ion (studies ->n'am nid 1ч and te-jurelevant ro man)

ЯГ-3

V. Co vf.> 111 , V. Di Ma то, B. Üdss.ini , S. Ftebessi , M . Coppola

In thetho naOver L:Caí эссl ncludofX-raysmon t hbThe ma:iadiatThe an.ova 1uainvest

f it» Id jf human and experinerin biological variable knownhe last few years, a line ofia, ha^ been set up to btudyncj obbprvatlons on late offe

to influence the susceptibi1Ity to tumorresearch at the Laboratory of Pathology,the effects sf exposure to neutron îrradctb (both neaplastic and non-neoplabtLc)

idtion -.'.ose and ЫЛ1 at low Josattenuated fission neutron

and af differont адеь. Graded single.ave been given to male BCÎF1 mice of

aqt? and to ammalb in utern at 17 dayb pu£t mi torn (pej .object of this study is to investigate the role of age ^>n the su^ci carcvnog>;*nesis and life-spûn shortening for different qualities о' 5 ь of data from over 3,000 animals i^ s t i l l in progress, but a pr

fcion has been iade during this year taking into account varijUa nnJpoigate whethei age at trt.-.it:T.?-it influences the effectiveness of low-en

d u

С .

i a t

a s

i

, p tf rM l

R. E

i o n

and

f u n

i b i l i t•ddimi ri

a t i

under

КМ:Л, Laboratory < Pathology, C.R.E. CasacciaP.O.B. 2400 - 00100 Roma, I t a l y Tumor

I Neution! X-ray• External Ir' Агл-intí

4 • • I - - .

ENKA

'-. . COVKI.L1 , V. lîl МДЛО, B. BASSANI, £ . REBKSSl, M. COPPOLA. P r o c e e d i n g s

VenuZbi, A p r i l l l - l r J , \c)81, IAEA UP, p r f ^ i .V. COVELU, V. DI MAJO, B. BASSANI, E. RbBESSI . Procvc iJ inos o f 7th ICRR,

J u l y í-У, ГПЬ ( L n p r o s s i ,

f a Symp is

Atnsjtordam,

HALY IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

"HadiaLion-induced лоп-disjunctio

spcrmatogenesis" irradiation : experiment•<

data on mice

P- Paechierotti

Data relative to the efficiency of radiation in inducing non-disjunction are

still very scanty particularly for germ cells of mammals. Considerations about the

role of these chromosome aberrations in producing spontaneous abortions and severe

genetic diseases in man make it necessary to collect further data and information

in experimental model systems for better estimating human risk.

Direct cytogenetical analysis of the chromosome complement in mouse secondary

spe

:y of different raeiotic or pi

dose of X-rays or neutrons has already been evaluated by this approach.

Researches are now in progress to determine dose-effect relationships at the

pachytene stage for 250 Kv X-rays or 0,4 MeV neutrons produced by the experimental

fast reactor RSV TAPIRO in operation at the Casaccia Institute. (C57B1/Cne x C3H/Cne)F1

male mice are used; dose range tested is 0.25 - 3 Gy for X-rays and 0.tÍ - 0.72 Gyfor neutrons. Preliminary results suggest a linear relationship for both types ofradiation and an RBE value around 6.

The observed correlation between numerical and structural (fragments) aberrationsat each dose tested has suggested that a direct damage to the chromosome structurecould produce non-disjunction events as well as chromosome breaks.

S. NOM ET ADRESSE fObTAUE OE L'ETABLISSEMFNT AVANT EUTPE^Rt!

ENEA, Laboratory of Toxicology, C.R.E. CasacciaP.O.B. 2400 - 00J00 Roma, I t a l y

8. sounceibl oc FINANCEMENT

ENEA

9 , DURE С DU PnOGflAWMC

oc- /..JSS2.£лСнЕ EHCOJRS-№1. œ*SZX3£3 А

гякидосххг:.ггssr^z? допстодах

Non-disjunction

Male meiosis

Mouse

Chromosomes

Neutrons

A. Russo, F. Pacchierotti, P. Metalli (1983), Meiotic non-disjunction induced by fission

neutrons relative to X-rays observed in mouse secondary spermatocytes. 1. The response

of different cell stages to a single radiation dose, Mutation Res. 108, 359-372.

Comparât! VL1 risk assessment of di f ferent muta ce ni t agents :[ow dosi? RFiE, quality factor and rt'l.ttîve risk of differentradiat ions.

EffWts of llxturn.ilI rr.idiation

3 AUTHORS OR INVESTIGATORS H.P. Lcenhouts .ind K-H. Chadwick

5. NAME AND MAILING ADDRESS OF ORG

Dr. H.P. LeenhoutsAssociat ion EURATOM-TTAL,P.O. Box 48NL-6700 AA WAGF.NTMGEN.

I n s t i t u t e for Public Health and Environment,Hi lthoven, Nether lands .

SPONSORING ORGANIZATIONS!Ministry of Agriculture and Fisheries,Commission of the European Communities

OURATION OFPROGRAMME

FROM- 0.V83TO \Z '84

6 DESCRIPTORSOR KEY WORDS

Radiation ef fec tsDose-effect re la t innsComparative r i sk assessmentMtít.ifienir aeentsRBE qual i ty fai tor

K.H. Qiadwick and H.P. Leenhnuts : Tlie Molecular Theory of Radiation Biolosy (1981)

Springer Verl.iR, Heidelberg.

IV.ENVIRONMENTAL STUDIES. PATHWAYS AND MONITORING

101

I '


Determinación de C-14 en efluentes gaseosos de Ia CNA I

2 ТЕМА GENERAL

Estúdios am-bienta] es.Vias y \igilancia ra-diolõgica.

3, AUTOHES O INVESTIGADORES

Ol ive i ra , Д.А.; Gomez J-C.

La estimaciõn de Ia dosis colectiva comprometida mundial debida ai C-14 indica que es_te radionucleido es uno de los pr incipales contribuyentes ai impacto radiológico g lo-bal derivado dei funcionamiento de centrales nucleares; en par t i cu la r , en e l caso delas centrales de uianio natural moderadas con agua pesada.

Se présenta una serie de mediciones de C-14 realizadas en efluentes gaseosos de Ia -Central Nuclear Atucha I . El método de muestreo u t i l i zado permite Ia determindciõn -de Ia actividad de C-14 como CO2 así como Ias formas gaseosas reducidas (CO e hidro-carburos), cuya relación se calcula en cada caso.

De los resultados preliminares se deduce que es necesario Ia implementación de mues-treos contínuos de ef l jentes con el f i n de obtener evaluaciones precisas de la a c t i -vidad de C-14 descargada al ambiente. Los resultados obtenidos muestran que existe -una marcada dispersion debido al regimen de operación de la cen t ra l , así como a emi-siones discontinuas aún durante períodos de operación constante.

5 NOMBRE V SEN

CNEA-CAE - Secciôn Radiactividad Ambiental.Casi l la de Correo 40 - 1802 Aeropuerto E?eiza - Argentina

7, O«GANlZAC'ON U OHGANIZACIÛN£S ASOC'APAS

С ION и ORGANIZAdONtS PATROCI

I12 1984

Х К Ш Й Ш - INVESTIGACION EN CURSO -ХПЕШШШХШСШЯШХХЖ

Caruono 14Efluentes gaseosos(Gaseous efluentsïLiquid scinti l lationcounting.Radiation monitoring


DETERMIHACIOH DC LA CONCENTRACION DE Rn-222 EN VIVIENDASDE LA REPUBLICA ARGENTINA

FUENTES DEÍRRAD1ACI0NINTENSIFICADAS POR LAACTIVIDAD HUMANA

CIALLELLA, H.E.; GEREMIA, R.fl.

Se están realizando estúdios para Ia determinación de Ia concentración de Rn-222 y susproduetos de decaimiento de vida media corta en viviendas de la República Argentina.

Eu una primera etapa se real izo Ia puesta a punto de los métodos a u t i l i z a r consisten-tes en: medidores e lectrostát icos pasivos, ut i l izando como detector TLD (F Ca:Dy) ymedidores pasivos que se u t i l i zan como detector f i l m de poHcarbonato con posterior revelado electroquímico del mi SITIO.

En la actuaüdad se l leva a cabo un p-ograma de monitoreo para determinar el nivel deRn-222 en viviendas ubicadas en d is t in tas zonas del país. Asimismo se tratará de determinar la relaciõn entre la concentración de Rn-222 y sus produetos de decaimiento tíevida media corta.

CNEA-CAE- Sección Radiactividad Ambiental.CasiTIa de Correo 40 - 1802 AEROPUERTO EZEIZA - Argentina

HGUNIZACIOM I' ORGANlZACIONES PATROCINADORAS

9 Q U P A C I O N DEL PROGRAMA

oE 1 198312 1984

10 SITUACION

ШШ&Ш - INVESTIGACION EN CURSO -

Rn-222Radiation monitoringBui 1 di ngsBuildings materials

ARGENTINA IAEA/HPRA/No.11 ARGENTINA IAEA/HPRA/No.11

Detenuinación de la tasa de emanaciõn de Rn-222 de colas demi fier îa de urânio y su importância radiológica. Я

2 TEMAOENEHAL

Estúdios am-bientales.Víasy v ig i lância radiolÕgj_ca.

Escribano, T.L. ; C i a l l e l l a , И.Е.

Se están realizando estúdios para i den t i f i ca r las emisiones de contaminantes a îa at-mosfera derivados de los procedimientos de explotaciôn de minerai de urânio.

En par t icu lar , se l leva a cabo la medición de la tasa de emanaciôn de Rn-222 en colasde nrineria de urânio y se évalua la implicância radiológica en la poblaciôn local en^las inmediaciones de las instalaciones mnero- fabr i les . Los resultados obtenidos seránrelacionados con e l contenido de Ra-226 en los resíduos sólidos con el f i n de propor-cionar elementos para ser empleados en programa de cálculo que estimen ei impacto га—diolôgico a largo plazo de los diferentes procedimientos empleados en ei manejo de losresíduos sólidos de ïa mineria de urânio.

5. NOMBRE V SENAS OE. LA ORGANIZACON QUE REALIZA t L THABAJO

CHEA-CAE - Sección Radiactividad Ambiental.Casi l la de Correo 40 - 1802 AEROPUERTO EZEIZA - Argentina

. ORGANIZAC1ON U ORGANIZACIONES PATROCINADORAS

DE . .3 19.83

A Д2 ., 1984

Ш К Х Х Я Х Х - INVESTIGACION EN CURSO -

6 DFSCR1PTOHËS О PALABRAS

• Rn-222Uranium mining andmi l l i n gUrar.ium wastes

TITULO v SUBT'TULO DEL PROGRAMA

MONITOR CONTINUO DE 1-131 EN EFLUENTES GASEOSOS VigilânciaRadio Uxjica

3 AUTORES O )4VíST)GADOBfS

Bonino, Aníbal; Tinkiel, José

. RESJMEN

Se proyec±6 un equipo para medicidn contínua de 1-131 en efluentes gaseosos. Comocondiciones de diseno se fij6 una liberaciôn diária de 1 uCi en un caudal de 300 l/min,y la posibilidad de programar ei intervalo de integraciôn y el nivel de alarma.

El principio de detección esta basado en la retenciõn de 1-131 mediante un filtrode carbon acfcivado y la mediciôn del fotopico de 364 kev. Dado ei bajo limite de detec-ción requerido y luego de probar diversas qecmetrîas de medición, se opto por colocar Iaunidad filtrante entre dos cristales centelladores de INa (TI).

El dimensionamiento dei filtro, ei caudal de muestx"eo y las características de losdetectores, fueron seleccionados con el fin de lograr ила elevada eficiência de contajepara el fotopico de 364 kev. El sistema discrimina I-131 en presencia de grandes canta-dades de Xe-133 y Xe-135, se diseno cuidadosamente la electrfinica asociada con el obje-to de lograr una buena resolución y aran estabilidad en los niveles de discriminaciãn.

El sistema présenta la informaciõn mediante registro contínuo de Ia actividad to-tal retenida en el filtro del incremento de dicha actividad en el intervalo de integra-ción prefijado. Ademâs sefializa, alta actividad en el filtro, alta actividad incrementaide eficiência en la instalaciõn del filtre y falia en el sistema contaie.

5- NOMBRE VStNASDE LA ORGANIZACON QUE REALl2A EL TftABAJC

Comisi6n Nacional de Energfa AtômicaGerencia de Proteccidn Radiológica y ScguridadAvenida del Libeitador 8250(1429) Buenos Aires - ARGENTINA

ROC'NADOHAS

1983

1984

10 S'TUAClÛNPROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONOISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARA PUBLICACION

- Iodine -131 detection

- Gaseons wastes

- Solid scintillator dete-ctor

- Releases of radioactivematerials

AUSTRALIA IAEA/HPRA/No.11 AUSTRIA IAEA/HPRA/No.11

t. T U L E ANDSUBTITLE

A t m o s p h e r i c T r a n s p o r t and R ' s k A n a l y s i s

2. 0ЯОДО HEADING

environmentalStudies

M.CE. Petersen, G.H. Clark

Development of atmospher ic transport models for ope rat ional and act- id un La" ' from nuclear facil i t ies so that the stochastic

timization of radiation protection.

5. NAME ANO MAILING AODRESS OF ORGANIZATION DOING THE WORKEnvironmental Science Division

А.Л.Е.С.

P.O. Private Mail Bag

Sutherland, NSW 2232, Australia

7. ASSOCIATL i ORGAI

8. SPONSOHING ORGANIZATIONS)

9. DURATION OPPROGRAMME

FROM. 1/.ЙЗTO: \3I -84

Ш.PROJECT - RESEARCH 14 PROGRESS -

яииадлихканживгаюихин

Atmospheric transportprocesses

CoJlective Dose

TlTt.£ лнО Su«TfTLt

A large volume îonization chamber systemfor environmental monitoring

2. ИОАО HUO'IC

Environmen tal

Studies .

K.E. DUFTSCHMID, J. HIZO, J. WITZANI

In view of decreasing tolerance level contmously increasingaccuracy requirements for environmental monitoring have forcedthe development of such equipment to its physical and technologicallimits. Although îonization chambers inherently provide optimumdosimetrie performance, GM-counters are most widely used for thisapplication due to the much simpler electronic circuitry required.Steel-walled high-pressure ionisation chambers show a rather poorenergy response with distinct low energy cut-off.

An lonization chamber with 120 1 volume operated at atmosphericpressure has been designed and tested. The chamber is made fromnearly air equivalent plastics Tiaterial and operated at atmosphericpressure. With a wall thickness of 3 mm secondary electron equilibriumis achieved up to several MeV. The wall absorption for low energyphotons is compensated by a thin layer of Al deposited on the innersurface of the chamber. This provides an energy response of+ 2 % between 30 *eVeff and

6&Co.In connection with our digital current integrator NP2i00 withmicroprocessor circuitry doserates m the range of 2 nSv/h can bemeasured with a s tandard deviation of 0,5 nSv/h within 1000 s inte-

S. NAMf ANO fc i Of OAGA

Austrian Research Center Seibersdorf.Lenaugasse 10A-1082 Wien

7. ASSOCIATES O"Ci.MiiAT1ON(S!

5.

Large volume lonizationchamber.environmental monitoring

FROM:1.82TO: 12.85

i Prototype chamber developped|and tested. Development of1 electronic unit in progress.

DUFTSCHMID K.E., HIZO J. " Secondary Standard Iomzation Chamber"System* Vô^VnViroVmentVÍ^oVimêVry^^s^Symp . of IMEKO Technical Com .

on Metrology, Leningrad, Sept. 1981.

S BELGIUMо IAEA/HPRA/No.11

Development of an environmental dose model for routine and/or

accidental releases of nuclear installations,

3. -

J.G. Kretzschmar, P. Govaerts, Ï. :]ertpns, G. Dc Baere, J. Vandervee

The existing bi-Gaussian dispersion code IFDM (Iimission Frequency Distribution Model)calculates short-term as well as long-term concentrations and deposition values, aswell as the statistical characteristics of their ensembles, in whatever receptor in-fluenced by one or several sources. The DOSDIM (Dose Distribution Model) code usesthese outputs, or intermediate results, to calculate individual or population dosesdue Co routine or accidental releases from nuclear installations. In the code thedifferent pathways are included as well as the complete emission inventory (constantor variable as a function of time and space). Different sensitivity studies arecarried out in order to evaluate the influence of the input parameters upon the resultsof the code(s). At the same time comparisons with similar codes are done.

SCK/CENBoeretang 200B-24OO Mol Belgium

1 Û . E-r.

5. OESCW'-EU*! OU "OTS С-

Accidents

Environmental doses

Mode1ling

P.'.Goyaerts.et.aJ,, ,(1?9?), . АррЦсаЦсц.о£. the.DOSDlM-model to assess doses due todeposited material subsequent to an accidental atmospheric Telease, presented

' • -af the'CEC'Seminar'on' the'Transfer-'òf Radioactive Materials in the Terrestrialf. subsequent, to. an. accidental release to the atmosp'iere,Dubl in 11-14.4.83

BRAZIL IAEA/HPHA/No.11

1. TITULO Y SUBTÍTULO DEL PROGRAMA

Natural Matrices for Uranium, Thorium and 1 otasoium

determination.

2. ТЕМА GENERAI.

Environmental

Studies. Pathwa,

and Monitoring Б.


Antonio Eduardo de Qliveira e José Luiz Santana de Çarvqlh

A. RCSUMEN

The present research deals' with measurement-and preparation méthode*

using geoahemxaaX samp tes (mineral ores) to obtain standard reference

materials for uranium y thorium and potassium determinations. These na-tura I

matrix reference materials are normal ty used as test с ample в-, in des tructiVi

assays or as standards for the calibration of instrumente.

Initial lu five measurement methods will be used: direct measurement

of natural датща radioactivity ; neutron activation and gamma speotrometri

neutron activation and beta cozinting; atomic absorbtion spectrometry and

spec trophotome try. The mineral samp les come from different "Brazilian uranii

mining regions.

INSTITUTO DE RADIOPR0TEÇÃO E DOSIMBTBIA

ÀV. DAS AMERICAS, Km 11„5'Сх Postal 27025

CEP: 22.602 - Rio de Janeiro - Brasil

8. Ol GANIZACION U OHGANIZACIONES PATROCINADORAS

9. DUMACION PE L rnoCiHAMA

:U ; ..«S....

10. SlIUftClOfPROYECTC--

6. DCSCRIPTORES О PALAUHAS CLAV

LIRAtlIVM ОКЕ

THORIUM OHE

POTASSIUM ORE

MOCK SOURCE

NAT VUAL MATRIX

TFCHllIQVB OF AriAUSIS


átermination of U, Th etc, in the Olinda - PF

phosphorites by means of instrumental neutron

activation analysis and gamma epectrometry.

Environmental

Studies .Pathway^"

and Monitoring

Jose Ubiratan Delgado e Jose Luiz Santana de Ça.

4. Hi SUM EN

A technique for analysis by INAA for Uy Th and other elemental

constituents in phosphorites ie being developed. The knowledge of the

presence of these constituents in most mineral matrices is of fundamental

importance in nuclear technology. This justifies the use of on accurate

technique which will generate a large amount of information about these e-

lements3 from small sample. Samples and standards were powdered to 200

mesh and packed with, special cave, in order to avoid contamination. They

were irradiated for 10 to 40 minutes in a thermal flux of aproximately

10Ï3 n/cm^.s. Two hundred mg aliquots of the irradiated material were

transfered to polyethylene containers with apropriate geometry in order

to perform gamma radiation measurements. The measurements started after

3 days of "coolinfj" and lasted for 4-S weeks. The gamma radiation countinc

was made with an ORTEC model GMX-10180 detector of 60cm3, during periods

from 0j5 to 6 hourв.

TNSTITUTO DE RADIOPR0TEÇÃO E DOSIMETRIA

AV. DAS AMERICAS, Km 12,5 Cx. Postal 37025

CEP. 22.602 - Rio de Janeiro - Brasil

1. QHGANlZACION U ORGANIZAC1ONES ASOCIADAS

8. ORGANlZACION U OfiCAN)ZAC'ONE5 РЛТПООМДРОЯАЭ

9. OURACION DEL PROGRAMA

OE .. 0.6. / . J.S....A .12 / S3....

10. SlTUACtONBEUTCECTD - INVESTIGACION EN CURSO -

6. i

INSTRUMENTAL NEVTROS

ANALYSIS ACTIVATION;

PHOSPHORITES;

SPECTRCMKTRi GAMMA AND

URAKIVM ORE.


2. >UI«IOUI £-(»-( n*l_í|

W i ï i t A . ( J ) , ;•:•-:.\\гп О ) , ъ-г--:\и\. ( . . ) , с о и . ч о . ч ( í - )

Population: du Suri-Г.-t de la ïм- ir» £Í: . í rci . l . L'é

cr les pri r-c ipal c-i ; our со: de••'• •-•'n.icec ш fai l do 1-1 ,,..'te '•: sent i<. 1 lerrîit :c i i v i l i i qu: le- £•-*:. '.rci.t - t< elude* copsu-tt- '•: MTit K. 1 lcrr<jiit :

'î ir.vc-dt c r i e r , lo,;.ii i:or et rrtrm î ' r i - .or ]fr Л j f f t rt-nX i.h Lourcvi de risque1. \,7 'z VIA Í L-L(Kr.r. с 11 f ' i 'j;io:i. 1-11 e". ;ii'uvf-i,t étr-J d 'oriî iiti п.иагч"^! It-, indu-,! r i pi ït-, r id icule c»u î j-'t-smi dt've lcpjiL-mt rit. С ci, ri-.fJUfS '.ont rnClo'io£J(;iJer, ou nori radioloîquus ;i outir.t i f i e r ] ET r i ' que', cci-j-c; ptîtlunts :- r.oit dirtiCtt-mt'-rit A peirtir de s te t i^t iques r-xir^tantcb ou d'enquêtes d rc-,ïlisor ;- soi t indirfCi(,iritT.t par 1er. nui1 ,inrt-s qui PU sont à l ' o r i g ine , ce l l e s -c i étant cxprimóüsen TíT-nsi? de concentra!-io;i des i '1'ronts polluontr: ou en te-rme d'exposition d ces cléments.Dans ce cas, Iti cucj:.ti f ïcation dti. nuiâncei*. rt-sulte :.cit. d'évaluation's théoriques fondé'T-Mir 1 ' ut î 1 i".."ition de тойГапг, LOI t de Kit*:, tire s pffee tuf-os au niveau des sources, de-s émis-r;îo:"-,, de 1 Vr.vircr.rierx-nt ou de 1 'ïio-.ne ;

. à évaluer 1er d-'irinu-nts õc^nciés aux risquer, e t aux r.ui:,uncfs, q u ' i l s 'agisse de d i t r i -mtT.ts ^-iritairci" ou dt- détriments au sein de la region, donc de la population, étudiée.

Í 'autre;, pr ol ouijt-' ic-ijti. '"ont С а1-,-п>"'П* cnvîru^és, lairt du côté de l 'appréciat ion (le laf rvcp: :on d'-s i l t.jer pvir 1er. populations сст.сегп'-е.ч que celui de l 'évaluat ion det- coûts

it1:, di í f -''rf-Titb ('''n iini':,^ 11 di""; coûts ces ir/ûrfi do prot<-ct icii c i vigueur.

!J; f ft-rent.:;. serviras de l ' I r iLt i tu t de Protection ft de Sûreté Nucléaire participent à ceproEra-rae : SHI (Л. CKAL/.5REYSSE), SÎ:KL (A. GPAUBY) e t SLGP (JP PAGEE).

1..Д. - I n s t i t u t de Protection et de Sûrc-té Nucléaire'pmxcniCTiX de- Protection Sanîiôire - SKR/EEGP

r.° 6^22&0 rON'IbNZ-Y AUX )<OGi:S

B. SOUWCIISI OI M"* i .

СП.A. + C.C. L.

О ( : „ 1980

«, •

10. iЯ Ш * -RtCHSRCHE ÎU COURS -

ILLIMITEE -

fuelCharbonNucltaireEnviroii^cï;.- ntPollutionPi squeb r'roff.Population

1 1 . f1 .i'OUVK.i.C _( A) c-t a l , I n t é r ê t de la comparaison des r i rques dans l e dévelopf oir.eiit iconcriqui

et pi'Cjiorlt ienr, peur ими approche au niveau r é g i o n a l c-t ?. ANOUt-HOT (Г) et .^l, Impact radiol"-£Íqi:£ ce; :. и *". ni : , ' ph'rir. i irp d'u:.e ct-r.trale a j cîi^rbcn. Congrès dnrur-l 19S2-'- : Ъл1. I,a(. (.",7 ;Г.; or. d"^ г : ' сд:",- ч ' ос i *'- <": J-X grt-Tide? ci e t ivî*. Гт t ur«iiiiC'5 - Avijr.^ri 1 9ЬЗ

--1. f-]" : '• : "Ы ( J ) « t_ aj_, i'v,-.Vu,tî irr. fî'"' i_ci,' ('r.ucncer, r..iii t a î r e s drr к > 1 : СКГ.Г. 1 'at: J -pSí r

FRANCE IAEA/HPRA/No.11 FRANCE IAEA/HPRA/No.11

PREVISION DES CONSEQUENCES RADIOLOGIQUES D'UN REJETATMOSPHERIQUE ACCIDENTEL APPLICABLE A DES OROGRAPHIESCOMPLEXES

Etudes de l 'envment. Voies d ' e x p o s i t i o iet de s u r v e i l l a n c e .

D. Robeau, M.T. Bast ien, N. Parmentier, M.С Blondin

Dans te cadre de la mise en serv ice d'un centre de prévis ions des conséquences rad io-logiques devant permettre de déterminer avec l e plus de préc is ion poss ib le lasdommages san i ta i res e t économiques subi ts par la popula t ion, l 'é tude des t rans fe r t satmosphériques après r e j e t accidentel est importante.

Le p ro je t présenté a pour but de q u a l i f i e r un ce r ta in nombre de codes de c a l c u l , quiont été développés par les "Etudes et Recherches Météorologiques" de la MétéorologieNationale e t le CEA entre 1980 e t 1983. Ces codes ont pour but :

- de déterminer heure par heure l a courantologie atmosphérique ã p a r t i r des mesuresprovenant des s ta t ions météorologiques régionales par l ' i n t e rméd ia i r e des ServicesMétéorologiques Mét ropo l i ta ins ;

- de su i v re , demi-heure par demi-heure, l e t r a n s f e r t de la r a d i o a c t i v i t é relâchée àl ' éche l l e régionale e t d 'es t imer les doses à la popula t ion. Ce modèle de t r a n s f e r test adapté pour t r a i t e r les cas de t r a n s f e r t dans des régions à orographie complexe

- d'associer à chaque dose ca l cu lée , l ' i n c e r t i t u d e avec laque l le e l l e a été estimée,compte tenu de la v a r i a b i l i t é e t de l ' é ven tue l l e méconnaissance numérique des para-mètres u t i l i s é s .

IPSN - DPSCentre d'Etudes NucléairesB.P. n° 6 - 92260 FONTENAY-AUX-ROSES

Météorologie Nationale

CE.A.

9. oumtt С

Ot: 1982

1985

10. CTAT O-AV»NCt"i"T: *Ï IBUtï - RtCHSf.CME EN COURS -

6. OESCHir-cui.5 OU HOTS CLfi

- Accidents radiologiques- Transferts atmosphériques- Météorologie- Doses aux individus de la

population

Atmospheric transport model fo r radio logica l emergency preparedness fo r complex1 1 "térr'a'îri'CrnTeVnatTo'naTméétVng'bh'Thêrmarnûcléar Safety, August 29-September 2,

. .1982, .Chi-cago.)2) Radioactive releases consequences in case of complex t e r ra i n : methodology for

applications of protect ion measures (6e Congrès IRPA-BERLIN. 198j).

EVALUATION DES CONSEQUENCES SANITAIRES DES REJETS RADIO-ACTIFS EN MER - IMPLICATIONS POUR LA SURVEILLANCE Etudes de l 'environne- ,

ment. Voies d'exposit ionet de survei l lance.

D. Calmet, D. Robeau, S. Charmasson, G. Vergniaud, C. Madelmont

La surveil lance des conséquences sani ta i res des rejets en mer est basée sur desmesures radioactives de cer ta ins b io indicateurs. L'échantillonnage dans le temps etl'espace de ces bioindicateurs est à l 'heure actuel le basé sur une étude pré l imi -naire de d i f fus ion f a i t e i l y a plusieurs années. L'étude s ta t i s t ique des résultatsobtenus au cours des 10 dernières années est en cours avec en outre l ' o b j e c t i fd'estimer certains facteurs de t rans fe r t s . Simultanément, le t ransfer t 'des radionuclévdes est calculé en u t i l i s a n t un modèle de courantologie pour la d i f fus ion et unmodèle prenant en compte les phénomènes de sédimentation. Un essai de va l idat ionde ces modèles sera f a i t en u t i l i s a n t les données obtenues par analyse s ta t is t iquedes résultats de la survei l lance ainsi que cel les obtenues par un réseau d'observa-t ion mis en place f i n 1982.


COMPAGNIE GENERALE DES MATIERES NUCLEAIRES (COGEMA)

'CE.A.

et. .- 1982» • — 1985

- ntCHïfiCHE EN COURS -

- Transfert radionucléides- Mi l ieu marin- Conséquences sanitaires

des re je ts- Facteurs de t ransfer t- Surveil lance de 1'environ

nement

Evaluation of the health consequences re lated with the radioactive releases fromthe French reprocessing plant of La Hague.D. Calmet, D. Robeau, С Madelmont, G. Vergniaud, C. L a f a i l l e(IRPA-BERLIN, 1984)

* selon le cas* selon le cas

1GERMANY, FEDERAL REPUBLIC OF IAEA/HPRA/No.11 GERMANY, FEDERAL REPUBLIC OF IAEA/HPRA/No.11

Investigations on decontamination and enrichment ofcesium-137, strontium-90 and lead-210, respectively,by handling and processing of meat

2. BROAD HEADING

Wagner, H.; Mirna, A.

ABSTRACT

Radiation exposure to man by various food stuffs depends also on the amount ofradionuclides ingested via meat and meat products, in this respect the influenceof handling, processing, cooking and curing of meat on the behaviour of the radio-nuclides Cs-137, Sr-90 and Pb-21O, as well as the corresponding inactive elements,ib investigaleci. B e s i d e s t h e s e uecuiiLdiiiiiidLiun effet, ьъ, t»rn iLumeiiL uf t cttiiudiLive

material derived from food ingredients, as spices, smoke and the use of mechanicallydeboned meat, is taken into consideration.

5. NAME ANO MAIUNG AOOHESS OF ORGANIZATION DOING THÉ WORK

Laboratory for Radioisotopes, Federal Institute ofMeat Research;0-8650 Kulmbach

7 ASSOCIATED ORGANIZATIONS)

GSF Research Center; D-8042 Ueuherberq/Munich


Bundesminister des Innern; 0-5300 Bonn


FROM: ÍP/ S3TO: . 9/ Я5


6. DESCRIPTORS OR K£V WORDS

Meat processing;radioactive contamination;Cs-137, Sr-90, Pb-210;food additives

Wagner, H., Mirna, Д.; Transferfaktoren Futtermitteï/FIeisch bei Rind und Schwein.Radioõfcologiesymposium; Berichtsband der Tagung am 15./16. Qktober 19Я1;13 p., Editor: Bundesminister des Innern; D-53Ü0 Bonn

Experimental investigations of the effect of buildingconstruction techniques with respect to dose reductionin houses of areas with enhanced natural radiationbackground.

Environmental studies

3 AUTHORS ОЯ INVESTIGATORS

H. Kiefer, E. Piesch , M. Urban, |_. Leidner

4. ABSTRACT

The aim of the research program is to determine the influences of differentconstruction techniques of houses on the exposure of the inhabitants tonatural radiation. Different types of houses will be investigated in areaswith elevated naturel radioactivity caused by geology or mining dumps.

5 \AM£ AND MAILING ADDRESS OF ORGANIZATION OO'N

Karlsruhe Nuclear Research CenterHealth Physics DivisionP.O. Box 3640D-7500 KarlsruheFedera! Republic of Germany

7.

SPONSORING ORGANIZATION(S)

Federal Ministry of Interior, Federal Republicof Germany,

FROM. IO/. 83T ° \Z! 85

10 STATPROJECT - (EARTIAIr QB-WNAI, BtPOW-WlTH Í4W Я НОП UNHMIX-CO-DISTfllSUTION ' • REPOflTSOBWirnTD TDITPOB С (CTTION

6 DESCRIPTORS OR <G v WORDS

Radon concentrationsin houses

Influences of differentconstruction techniqueson radon concentration

1

- GREECE IAEA/HPRA/No.11

1. TITLE ANDSUBTITLE "Transuranic Elements in the Marineenvironment"

A study on the concentration of Pu radioisotopes in the

Greek seas.

EnvironmentalStudies. Pathways andMonitoring.

S.Danali-Cotsaki and H.Florou- Gazi

4. ABSTRACT

In order to determine the Background levels of Pu in the Greek seas we started

our study by collecting samples from selected areas from the Aegian sea.

In this report the applied experimental methodology is, briefly, described and the

results, which have been drawn up to now, are reported. According to these results

the levels of pu concentrations in the examined areas are in the order of ixlO"15

Ci/1 (or 1 fCi/1). An assessment of the concentration levels of Pu radioisotopes

in the examined areas of the Greek seas, by comparison to other seas, is attempted.

Levels of Mixed Fission Products concentrations in samples collected from the above

areas, are also reported and discussed.

Greek Atomic Energy Commission, Health Physics Division

M.R.C. DEMOCRITOS

Aghia Paraskcvi Attikis - GREECE


This work is performed under the 23"<7/RB and 2317/R1/RB

Research Contract between IAEA and Greek AEC.


(as above)

9. OURAT'ON OFPROGRAMME

FROM: 91Tp: I? .81

10.PROJECT - RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR.PUBLICATION


- Transuranic elements

- Marine radioactivity- Plutonium concentration

in the environment

- Sea water monitoring- Actinides in the

environment.

1) S.Danali-Cotsaki : "Data on the Environmental Fadioactivity in Greece" CAEC/ERL

2) S.Danali-Cotsaki and H.Florou-Gazî:"Radioecological Studies in the Marine Environ-ment": a)Progress Report applied to IAEA, L) GAEC/HRCD-DEMO Report No 82/14,M8?.

GREECE IAEA/HPRA/No.11

1 TITLE ANDSUBTITLF "Radioecological studies in the MarineEnvironment"

A study on the concentration of mixed fission products inGreek sea waters and of Cs-137 in fish and sea plants.

2. BROAD HEADING

Environmentalstudies. Pathways andmonitoring.

3 AUTHORS OH 'MVESTlGATOnS

S.Danali-Cotsaki and H.Florou-Gazi

ABSTRACT

The concentrations of mixed fission products in sea waters and of Cs in fish

and sea plants are different for samples collected from different sampling areas.

This difference is more remarkable in the year when the level of the world wide

fall-out is higher, especially with regard to mixed fission products concentrations

in sea water samples.

Increases or decreases of mixed fission products concentrations in sea water samples

result to increases or decreases of Cs in fish and sea plants.

NAME AND MAILINCi ADDRESS OK ORGANIZATION DOING THE WORK


N.R.C. DEMOCRITOS

Aghia Paraskevi Attikis-GREECE

This work is performed under che 1940/RB and 194G/R1/RB

Research Contracts between IAEA and Greek A.E.C.


(as above)

FROM 01/ 75TO 12: 80


6 DESCRIPTORS OH K£V WORDS

- Marine Radioecology- Radioecology- Radioactive rollution of

marine environment

Cs concentrations

- Sea water

- Fish

- Sea Plants

1) S.Danali-Cotsaki : "Data on rhe Environmental Radioactivity in Greece" GAEC/ERL

2) S.Danali-Cotsaki and H.Florou-Gazi :"Transuranic Elements in the Marine Environment

a) Progress Report applied to IAEA,Kay 1080. b) GAEC/NRCD-ПЕМО Report No 82/10,1982

GREECE IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11

TITLE A N D SUBTITLE "Radioactivity of the Greek Lignites and

of the fly ashes"

Study on the radioactivity of the Greek lignites and the

potential rick to the population on account of their uses.

Environmental

studies.Pathwayс and

monitoring.

iTMORS OH INVESTIGATORSSusan Danali-Cotsaki

4. ABSTRACT

The natural radioactivity of lignite samples, collected from different areas of Grcoce

and of their ashes is examined, in order to determine the level of it and the potential

risk to the population on account of the multiple uses of lignites.

Local sampling networks have been installed in the areas around the electrical power

plants, operating with lignites, in order to study the contamination of these areas by

the escaped fly ashes to the environment.

Experimental measurements and theoretical calculations have been done, taking into

account different meteorological conditions (atmpospheric stability, air velocity etc)

and the specific characteristics of each one station, in order to determine the magni-

tude -7Г- in relation to the distance from the station.

The radioactivity of cement samples containing, as an additive, pulverised fly ash frot11

power stations employing those lignites, is also examined and conclusions can Ь Р drown

up, by comparison with international values.

5. NAME AND MAIL'NO ADDRtSB OF ORGANIZATION DOING THE WORK


N.R.C. DEMOCRITOS

Agia Paraskevi Att ikic- GREECE

7. TIONlSI


Greek Atomic Energy Commission

FROM: .6/79TO 4 / 8.3

PROJECT RESEARCH IN PROGRESS -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

- Lignites radioact iv i ty- Fly ashes radioact iv i ty- Natural radioact iv i ty- Environmetal radioact iv i ty- Radiological r isk to tin

population frorc naturalradioisotopes.

1) S.Danali-Cotsaki :"Results of environmetal radioact iv i ty measurements in Greece"Reported in the yearly report of the CEC, since 1979.

2) S.Danali-Cotsaki :"Research on the radioactive contamination of the areas around

coal f irerd power plans" - GAEC/ERL-105/227.1/04,1980.

Hole of sediments in the accumulation and transport of radionuclides In waterway* Environmental Studies

Pathways and Monitoring

UTHOHS OH INVESTIGATORS

Sesai M.V.K., Day *•*•. Eulkami 7.7., More E., Saut S.J., Matter V.M.,

A templing programme me concluded in suuer (pre monsoon) in the Bombay HarbourBay for collection of surface sea water, bottom sedimente and sediment cores fromabout 20 locations J-Qthe bay. Sea water and bot to» ее dim ente samples are beinganalysed for their '"Ce and 9Qsr contents. The results obtained so far indicate 2 toto 20 pCi/1 of 137ce in sea water and 2 to 20 pCi/g of 1 5 7 Cs in bottom sediments.Studies on particle size distribution and stable elements' analysis of the bottomsediments are in progress. The data are being used to obtain E. factors for rarioueelements and radionuelides and to assess the transport of radionuclidea from the bay*

«nvironaental Studies Section,Health Physics Division,Bhabha Atonic Research Centre, Bombay 400 085,India

8 SPONSOfll\ 3 ORGANIZATIONS

IAEA, Bhabha Atomic Bssearch Centre

PROMTO

1982

10 STATE Of

PROJECT - I ii IN гппппгт; -

UMITCO DlDTniOUTIQN

Enrironaental monitoring,transport of radionuolidessea water, sediments radio-nuclides accuaulation.

- INDIA IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11

t . TITLE AND SUBTITLE

'Salf-doaa and fadinf of CaSO. (Dy/Pm) and Caï, (»«turol) TLphoaphora in Bnrlronaental Radiation Monitoring.

2. BROAD HEADING

Enrironmental Studies.Pathwayв and Monitoring

3. AUTHOR5 OR INVESTIGATORS

1Ю1 LS.7.

4. ABSTRACT

A "ahirtdad atorage experiment" for eatiaating both the "eelf-dose" and "fading"of TL phoaphora under oonditiona akin to thoae faced in anriromiental Monitoringapplication» ia daaoribed. Daing this method, «elf-do», ratea of 0.52*0.10 (cr ) prid a"' and 1.16*0.02 (<r) n rad h"1 hare been obtained fer Ca», (natural) and CaSO,_ « . T", i t .ч л^*. —.—_*•_«,_ -*• 4C№ *л*> fli.aa тЛлалЬпта tiiwl out to Dfl

•adio-

rad h"1 and 1.16*0.02 («-) n red fl"1 hare been obtained fer uar- I natural; ало •(ST) Phoaphorai the thermal decay oonatanta at 25*C for theae pSoaphore turn ou27x 10* h"1 and 12x10"* h"1 respectiTely. Katimation of the self-doaea fro» r=»*--•otiTtty Eeuuraaenta of the phoaphora concerned ia aljo presented and the differencesexplained. А тегу high self-doae rate of 5.6 p rad h"1 «aa eatiasted by the lattermethod for a aaapl» of CaSO tTa) phoaphor.

Health Fhyaica SiTialon,Bhabha Atoaie Beaearch Centre, Eoabay 400 085.India

8. SPONSORING O R G A N I Z A T I O N S

Bhabha Atomic Keaearch Centre

9. DURATION OfPROGRAMME

FROM:../)981то ../continuing

PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION -•SUDMITTCD ГОП PUBLICATION

6. DESCRIPTORSOR KEY WORDS

TLD , Self doae fading,CaSO.lBy/Tm) , Caï(natural)i EnTirofia«ntalRadiation

1. fuel. Inatr. Heth. 197 (1962) 453-457

Study of Tranauranlea in the Tarapur Coaatal Enrironaent andBinding Charaeteriatlca of Pu in Soft Tissues of MarineInrertebratea

Enrironaental Studies)Fathwaya and Vonitoring

Caeadramoull S. and Bhat I.S.

Concentration of transuranle nuclidea (Pu, Aa, Ca) in Tarloua aample aatricaa(aeawater, a i l t , aeamed and marina organlaa) in the cuaatal enTironaant of theTarapur Atoaio Power Station теге inreatigatad. Diatribution of Pu in the coastalaedlment with distance from the effluent outfall i u atudled.

Preliainary atudiea on binding characteristic» of Pu in the soft tlaeuea ofoyaters, oraba, larita oryiarua and hepatopancreaa of Aplyaia Sp. пате been sarriedout. Strsn» aasociation of Pu with protein of aoft tiasue ia indicated. Interactionwith digeatire gland hepatopancreae of Aplyaia Sp. ia tualitatlTely different fromother tissues studied. Binding of Pu was different from other radionuclides like6OCo. " и . 9 0 Sr. 1 0 6 Iu, 1 3 4 * 1 3 7 C . m 1 4 4Ce.

NAME ANO V G ADDRESS OF ORGANIZATION DOING THE WORK

EnYironnental Surrey Laboratory»Tarapur Atoeic Power Station.Thasa Diet.,Pin Code - 401 504

ASSOCIATED ORGANlZATIONISI

8 SPONSORING ORGANIZATIONIS1

Ehabha itomio Reeearoh Centre


FROM.TO:

19Э2-1984

PflOJCCT - RESEARCH IN PROGRESS -

Тгапв-or ailles- Coaatal•nriroDMent


1 TITLE AND SUBTITLE

i l l India Rttur&l Background Esdiation S m j j Using TLDs

? BROAD HEADING

3.

l u b i I.S.T., Larid S., Bapat V.N., Sunta C.V. and Sosan S.Ï.

A study has been going en since two rears to шеавиге natural background radiation1»T«1 Tariations orar the entire Indian sub-continent; already Meaeureaents Ьлте beenooapleted (quarterly basic o»or a cosplete annual cyclejat 136 principal aeteorologicalstations using Mailed TIDs. Leering aaido the monasits ereast the cosbined «ata forthese 136 location» yield a m«an background radiation 1ет*1 of 82+27 sR y i (uncorrectedjfor any energy depeadenoaf fading» directional dependenoe etc. al l of which areeipected to be negligibly eaall). 1 report will be prepared at the end of the threeyear programas which is expected to yield a coverage of 200 stations ; population doaedistribution as wall as ssasonal Tariations will be discussed there.

AIL'NG ADDRESS OF OHGANiZATION DOING ТнЕ WORK

Health Physics Division,Sbabha Atcsjio Researoh Centre»Bosbdjr 400 065.


Bhabha Atomic Besearch Centre


FROM: ../.I960TO ../.1984

-

TLD, India , BackgroundRadiation , EnvironmentalRadiation

Hatural Radiation Monitoring In Swellings In An Area OfUraciua Mineralisation

ВПОДО HEADING

Khan À.H., SriTBfltava G.K. and Ragbavayya H*

Monitoring of natural radiation has been undertaken in different types ofdwellings in end around Jaduguda where India's first uranium mining and proceeeingindustry i* located.

The monitoring prograeme conaists of «raluation of external gettia radiation* radonand radon daughter concentration*. In electrodepoeition system has b»en used for rapidmeasurement of radon* With this method concent rations dnm to 4 Bq/m' can be estimated*Themdoo daughter concentrations are measured with Kusnets'a method* The preliminarymonitoring data indicate that gamma radiation in the township dwellings averages about0.15 pGy/hruid in the rural dwellings near the uranium tailings pond the average isabout 0*3 uGy/hr* Badoo and radon daughter concentrât ions range from 0*004 to 0*06 Bq/mpand 0*4 to 7*3 mWL, respectirely in both types of dwellings under normal conditions.Teaporal variations are significant. The emanation rate in a brick and cement dwellingi s estimated to be of the order of 1 mBq/m<2 sec. In closed rooms about two fold buildup|in radon concentration takes place orernight.

NC ADO H ESS QF ORGANIZATION DOING THE WORK

Health Physics Unit,Jaduguda. Singhbhtun,Bihar,India.


Bhabha Atomic Research Centre

DURATION OF

FROM

то- .continuing

PROJECT - ПСССАПСП IN PnOGf

• SUB Mt-TT С D-T-Oft PUBLICATION

R&diation Monitoringuranium Mine

- INDIA IAEA/HPRA/No.11 ISRAEL IAEA/HPRA/No.11

TITLE AND SUBTITLE

Кадоп Daughter Product Activity U n l i in Son* Нов-QnmluaЮма la Iadia

2. BROAD HEAOlNt

ESTlronawtalStudi**, pathway*"and Monitoring

IT

lair» Ï.B., Bapen, C D . and Baogaxajan, C.

4. ABSTRACT

Д aaapl» «urn/ ot nan-uranium aluei la India for air-borne radioactivity du* tonatural radoo decay produota la continuing. So far four coal aine*, thraa laad andalno i t i u i four gold aim» and аатап eoppar mine* from variou» location» ьат* Ьаапmonitored. Bit rama of average aotirity larala obaarrad a n aa follow»!Bang* of air-bom» activity Kiabar of adota Type» of Min»»1«т«1» la pCl/1(equilibrium equivalentconcentxvtlon/

leea than

3

40to

to

40

120

10 4 coal mlnea and6 metal Min»»

a l l aetal Mine»

both natal aine»

In one of th» aatal mlnea in the category 40-120 pCl/1, the actlrit/ in the maisventilation ratum air way waa 50 pCl/1 and thoae at different working lerela variedfrom 40 to 120 pOi/1, whareaa in th* other aine the general level* rarled from 5 to30 pCi/1, with a few location* having levelihlgher than 40 pCi/1. lhe programme willcontinue to cover вюге alnea.

5. NA

Air Monitoring SectionSivlaion of Radiological ProtectionBhaoha Atoalc ВенагсЬ Cent»Тгоаьау, ВовЬау : 400 085, India


Shabha Atomic Baaearch Centra

FROM: 1. I t 9 7 9

то K . i лэдз

- RESEARCH IN PROGRESS -Hfte^MMianit^ftarMt a r t е и м и и и i I M H

DESCRIPTORS OR

Radon, Non-Oranlum Mine»,natural radioactivity,ccml mlnea, Metal minea»

«•ir, Ï.B., Sapen, CD. and Bangarajan, C , High Badoo lerele I « t , c t , d la 3 o mlonJJranlu» Mine* in India. Proeeedlnga of Second Specl»l Sympoaim on naturalRadiation environnent, Bonbay, January 19-23, 1981, pp. 114-118, Wiley Eaatem

1. TITL» ля* suann»Radiological Rieka to the Population Following Penetrationof Radioactive Fallout into Food Chains Environmental Studies

(IV)

X лЦТМОЯЖ OA INVItTieATWIia

Koch, Jean and Tadmor, Jacob

. *»»TI«ACT

Radioactive fallout presents a phort-tem. risk due to Its direct deponltlon onagricultural crops, as well as a long tera risk resulting from its deposition on souand subsequent uptake by crops. A dynamic model, RABFOOD, was developed in thepresent study, based on different existing models. The model simulates transportof Che fallout radlonuclides through agricultural food chains to man and evaluatesthe radiation doses resulting from consumption of contaminated food. Transport wasmodeled through compartments representing various cnvlornmental elements or foodproducts i.e. air, soil surface, soil root zone, deep soil, plant surfaces, plantinner tissues, milk, meat. Internal radiation doses (whole-body weighted doses)were then estimated following ingestion of contaminated foodstuffs. A case studywas performed: radiation doses to man, resulting from short term and long termconsumption of contamianted food products were evaluated for soil contamination bydifferent radionuclldes. A sensitivity analysis vas performed for the main modelparameters. It showed that the radiation dose is sensitive mamly to changes Insoil contamination levels and changes in parameters characterizing Initial falloutinterception and resuspension.

Soreq Nuclear Research CenterYavne, 70600, ISRAEL Radiation Accidents

Assessment of DosesContamination of Food

Chains

F/«OM- 3 1&2

TO: 5/S3 SU1M1TTEC FO« ".«

;\. •(*<iif*ictf o» «flCiM

ISRAEL IAEA/HPRA/No.11

Radiological Risks to the Population Following Penetrationof Radioactive Fallout into Food Chains Enviionmcntal Studies

(fV)

1 AUTHORS ON iMVItTtOATOM

Koch, Jean and Tadmor, Jacob

Radioactive fallout presents a ^hort-term risk due to its direct deposition on

agricultural crops, as well as a long terra risk resulting from its deposition on soil

and subsequent uptake by crops. A dynamic model, RADFOOD, was developed in the

present study, based on different existing models. The model simulates transport

of the fallout radionuclides through agricultural food chains to man and evaluates

the radiation doses resulting from consumption of contaminated food. Transport was

modeled through compartments representing various enviornmental elements or food

products, i.e. air, soil surface, soil root zone, deep soil, plant surfaces, plant

inner tissues, milk, meat. Internal radiation doses (whole-body weighted doses)

were then estimated following ingestion of contaminated foodstuffs. A case study

was performed: radiation doses to man, resulting from short term and long term

consumption of contamianted food products were evaluated for soil contamination by

different radionuclides. A sensitivity analysis was performed for the main model

parameters. It showed that the radiation dose is sensitive mainly to changes in

soil contamination levels and changes in parameters characterizing initial fallout

interception and resuspension.

Soreq Nuclear Research Center

Yavne, 70600, ISRAEL Radiation Accidents

Assessment of Doses

Contamination of Food

Chains

8. I'ONSOAlNG a

РЛОМ: 3- / U2

ТО: S-/-S3

11. T'ftMCffO'.

олом ЙО^CNLlMTHSOISlkeUijdN

SV$Mt7TBÜ POU JU8LJCA71ON

"i» i*ioaATO«v


<H i-t of i t a l ian pouulal i vi Tourneudif.s.

С. Ma s t ino, £!. Piigd n i n, Г. S,mt a ron i

In the framework of the studies finalÍ zed to the évaluât ion of the radiologu al ехроьигif the Italian population to the ar t i f ic ia l sources of ionizing radiations, t lie evaluation

of the contribution of natural sources is a preminent task. Among other studies on externaland internal exposure, the measure of the long lived bone-seeker alpha emitters has beeninitiated on the justif ication that their dose contribution through W3ter and diet may

" " - - - - buinn mzea on еле j u s t i t icat ion tns t tneir aost* contribution tnrough water and diet may ht>not ins igni f icant . In I t a l y , 95% of the water supply is fed from underground deposits, but226[{Д Jevels higher than normal, arc only seldom encountered. Nevertheless cer ta in groupsof population, characterized by consumption of locally produced food, might receive higherArises from " " R t i entering the food chain through underground water, depending on the

:ul iar geological c h a r a c t e r i s t i c s of Central I t a l y (soi l r ich in natural radionuclides

popdosepeculiar geolog ^..„.-- .„_-„- „.. -,

by a factor of 5 -i- 10 compared to the rrustal

A nationwide sampling 1 been carried out in the past years to с

NOM ET ADRES'E Г

ENHA, PAS-SCAMB, C.K.L. CasacciaP.O.B. 2400 - 00100 Roma, I t a l y

9. DUREÊOUFÍlOGRWi.

oc- J /Л98Д..KF-C^SbChE EN CO'JRS

R*r;*OHT PAflTiEL rzzrZDIFFUSION C T : S 3 ^ ; Í . " lH.tV.iTCRAPPORT ССКЛ.'!; POUR ruSUCA

Z ITALYO\

IAEA/HPRA/No.11

"Plutonium transfer from environment to man" Environmentalstudies. PathWays and monitorin;

3. AUTEURS OU CHERCHEURSG. Santori, G. lngrao, G.F. Clemente

The aim of the research programme is to obtain information on the actual environment

al levels, pattern of movement, distribution in typical ecosystem and burden of the

general italian population of plutonium, in order to determine the radioprotectional

significance of any release of this radionuclide under various environment condition.

The fallout plutonium content have been measured in five diet samples collected in

various region of Italy. The yearly dietary intake of plutonium in Italy is of the

order of 1.5 pCi, in good agreement with data available in other countries. Plutonium

concentrations have been also measured in many autopsy samples (liver, bone, lung,

kidney, spleen), collected from single individuals. The concentration data confirm

that most of the fallout plutonium is retained in the skeleton and in the liver of the

considered subjects.

ENEA, Continental Environment Laboratory, C.R.E. Casaccia

P.O.B. 2400 - 00100 Roma, Italy

8, SOUWCEiblOe FINANCEMENT

ENEA

ОС: .._ /....1919

10. e

- KF-.CHShChE ENCO'JRS-RAPPORT PARTIEL CZ2SZZ3&3ADIFFUSION C T S U S K ? !ШМ1ТСЕ -RAPPORTSOUt.'.'ZrOL'R П'ЗИСАТЮЫ

Internal contaminationManPlutonium


1. TITRE tTSOUS-TlTHE

"Tritium transfer from the environment to man"

2. KUeniauE GEKtnEnvironmental

studies. Pathways I

and monitoring

P. Belloni, S. Di Pietro, G. lngrao, G.F. Clemente

The aim of the research programme is to obtain information on the actual environmental

levels of tritium, its pattern of movement, distribution in typical ecosystem and burden

of the general italian population in order to determine the radioprotectional signific_

ance of any release of such radionuclidtj under various environmental conditions. Tritium

content has been measured in many environmental samples representative of different

continental ecosystems. The results obtained indicate that the organic bound tritium may

play a very important role in the long term behaviour of tritium in the environment. The

fallout tritium is measured in autoptic samples collected from individuals of the gene-

ral italian population . Tritium organ distributions in liver, kidney , spleen and lung

as a function of various parameter (sex, age, etc.) are under study. In autoptic samples

tritium has been measured both in the acqueouS and the organic fractions to ascertain

the relative importance of the tritium concentration in the two fractions. Preliminary

data on НТО concentration in autoptic tissues show a large variability among the various

subjects and the various organs of the same subject, suggesting that the tritium in the,

water portion of the soft tissues could not be homogeneous when low-level chronic

exposures of man to tritium are considered.

ENEA, Continental Environment Laboratory, C.R.E. Casaccia

P.O.B. 2400 - 00100 Roma, Italy

ENEA

; /..1.2.7.3...

. _ J

10. (Ç - r r c H S ^ C h E EN COURS-RAPPORT PARTIEL CC£S£zr;w£3 ADIFFUSION ZZZSSISSiSS ILLIMITEE -RAPPORT SUUf.'TfCC'R PUBLICATION

Internal contaminationManTritium


1. •mMnsous.TiTM T h e behaviour of radionuclides in themarine environment along the Italian coasts.Part.1 from yonte Circeo to the Gulf of Neaoles.

Environmentalstudies

ÏÏ

3.Brondi A., Damiani E.

Zurlini G.

Ferretti 0., Papucci C.

• nîS'JWE T h e sedimentolûRical behaviour of the radionuclides in the marinesystem facing the Gari^liano Nuclear Power Plant has been investigatedduring 1980-83. The aim of these studies was to find the influence of thecoastal-geomorDhology on the distribution pattern of some radionuclides(i.e. Co, Cs) and to predict, for different coastal^ones, t.ie possi-ble location Of the highest contamination levels. The results show thatthe radionuclides associated with terrigenous particles tend to depositin the zone of the sea botton subjected to low wave energy. As a conseouence in the low coast environment the concentration of radionuclides is verylow in the sandy belt close to the shore and the highest concentrationsoccur seaward in the next belt, corresponding to the first denositionalfront of terrigenous particles (area facing the Garipliano river mouth at40-70 m depth). In the cliff coast the highest concentration of radionu-clides occur comparatively closer to shore. Because of the greater deoth,the fine particles nay indeed Ъе accumulated very near to the shore line(Gulf of Gaeta: bot[?dnside and external part).

5. MOM E

!NEA-CREA - Laboratório Oceanografia e Pisica delMare-Cas,Postale 19030 LA SPEZIA (Italia)

7. ETABLISSEMENT (SI ASSOCIEIS) AUX TRAVAUX

8. SOUrtCf(S) Of FINANCEMENT

Я, DUREE OU РПОСПАЫМЕ

DE: /.д ; _ J, „

10. ETAT O-AVANCEMENT:

ЩЩЩЩЕ - RfcCHEhChE EN COURS -RAPPORT PARTIEL ЧШЩ^тЖ АDIFFUSION М Я М » ILLIMITEE -RAPPORT SOUf.'.IS POUR PUBLICATION

U MQTSCLiJ

Coast

Radionuclides

G e omorph ology

Sedimentology

Anselmi В., Brondi A., F e r r e t t i 0., Pawcci C ,Connessioni t r a ^pornorfolofia, franulometrie dei sedJmenti e distribuziondi radionucl idi in 7one narine subcostiere.AIRP AnnaT1 di RadionrotezioneVol.IV FaHc. uniro t par. Ю9-130 Dicembre 1983.


LOCAL SCALE ATMOSPHERIC DIFFUSION AT A COAFTAL

SITE IN THE PRESENCE CiT BREEZE EFFECT

2. WU^n'QUEGESERALf i

Environmpnfal

studies . Exposa 11.0

pathwys and mon 1 ton r

3. AUTEURS OU CHCflCHEURS

P.CAGNETTI, V.FERRARA

The research is divided in two main phases: during the first phase a

series of experimental meteorological campaignsat a coastal site will

be carried out in order to study the atmospheric behaviour under breeze

conditions (internal boundary layer, breeze wind cycle, wind and tempe-

rature profiles over the vertical and so on) and to evi dent i ate correla-

tions in typical land/sea breeze si tuat ion between parameters which are

readily accessible to measurements and parameters which are more

complex to measure or to record (i.e. turbulence, heath transfer.bourdar;

layers, etv.). During the second phase it will be carried out appropriât,studies about a suitable diffusion model, if possible not complex andnot requiring a long computer time, in order to predict the environmentaconsequences from a hypothetical accidental release (prolonged release)of radioactive material for LWR power plants located at a coastal siteand in presence of sea/land breeze conditions.

E.N.E.A. Dept. PASCRE CASACCIAР.П.В. 24ОО OO1OO ROME Italy

E . N . E . A . - C . E . E .

A •_ £. .2 9.8.4 ....

- RfcCHÊFiChE EN CO'JRS -RATi'ORT PARTIEL Ç2ESZT££3£ÎADlf FUSlO.4 CnsaSliST ! Ш Ш Т С Е -RAPPOKT SOUf.'.'S PQL'R PUBLICATION

6. (

- Atmospheric diffusio:

- Breeze effect

- Coastal site

- Meteorology

ГГ ITALYoo

IAEA/HPRA/No.11

M Y I I É P O S - I T H ' N OVKH ТНК SKA AND Í T S Г MPI. I CAT [ l'Ni-! . HUQHlÛU£ClMB/L

r ГГе~

Knv i t onmont n 1 , J_ys t u d i e s . !E x p o s i l i on p a t hwy«iinci mon i i o n riy

3. AUTEUR*; nu curncHtuns

P.ГAGNETTI, V.FUHHARA

SlarLing from the experi mt-nta I met euro I "pi ca 1 data col lee t ed over- the

цеа in the framework of an othrr contract with CEC-DG XI : icontract

SRO27-I), I ho atmospheric behaviour and characteristics over the sea

will be st udi e d. Those studi os will be carri ed out tо improve t he

underst and i ng of some charact eristic peculiarities of the 1owor

atmnspheri с 1 ayors over the sea relevant t o depôsifi on évaluâti ons, andto establish possible correlations between those parameters which arereadily accessible (wind speed, insolation, wet and by temperature, etc.and those parameters whi сh aro fundament ai in dopositi on studies but noteasily available (mixing height s, stabiIity condi ti tins, deposit ion,

velocity, etc.). In a secorttphase a modf>l will be pot up which takes int

account the characteristi с behaviour- of the lower atmospheric layers

over the sea and whi сh is abie to estimate depoai t i on for safet y

évaluât i on s , start i ng from an hypoí hef~ i с a I acci dental re ! еаяг t о

atmosphrrè both of short and prolonged durât î on. Fi nally, assumiпц somebasicaï hypotheses the possible consequences to population exposeddi rectely or i ndirect ly to sea water сontaminat ion (i ncludinji sea breezefffocts) will be oxtimated.

E.N.E.A. - <-ep.

CRF, CAFACCIA

POfl 24OC Ooinu

ENEA - CEE

A : - 6 ..J. . Л 4

- fi'.CH£i>CHE EN CO'JRS-

DIT F US! ON C n s S G i S ILLIMITÉE-ЯЛРГОКТ OQ'Jt.'fZ POUR PUBLICATION

6. DtSCRIPTEUOs OU "O"S "L.5

- Drv deposition

iion by úrydt-poFi 11 on


1 . •

VIE AN ANT) KXTRKME HA I S F ALL *-HJUFNCE^ ANAi.YS I i- TN Sf-KbRiiPKAN S- [TEf- Ff»[( A F T T Y FVAI . l 'TATi HNS (>F WA^H'H'TAND WI-.T Ш - p í i M T l o N

2.Knvir

'QUEOIMWILI ТС7~onment n I j JV_

5-.Г Uftl t'S .

Exposit i

and mon i i

!

i hwy?

3. AUTCUns n\J CtitriCHtURSP . CAGNETTI , V . Ft-НИЛНА

•S. ncs-jMtT he г e a l ) vt i e ova I u a t i on , w i t h a j j i v e n a c c u r r o n c e p r o b n b i 1 i ( v . o f (weta n d d r y * d e p o s i t i on fo1 L owi ng a h y p o t h o t i c a í a c c i d e n t a l reÏcase o f r a -

il г o a c t i v 11 y t o t he a t m o s p h e r e , i s t h e s t a r l i n g po i n t f o r a l l t lie« u b ^ c q u e n t a n a l y s e s o f ( h e t r a « f e r t o man o f t h e d e p o b Ï Í ed a c t i v i t y.The wet d c p o H i t i o n , i n p a r t í c u l a » c a n bo i n f l u e n c e d by l a r g e e r r o r s

d u e t о a n un s a ' i s f a d n r v know! ed.ee o f t h e p o s s i b l c mt*nn and rxt г стоr a i n f a l l s a s a f u n c t i o n b o t h of t h e c l i m a t o l o g y o f t h e s i t e a n d of s a m p l it i m e or the durai i o n of thr- r e l e a s e s .i-o, t o r e d u c e t h e p o s s i b l e i r . c e r t i t u ir-s щ t h e c a l c u l a t i o n o f maximum wetd e p o s i t i on f o r s h o r t a n d p r o ] onti f 'd ri* 1 e a s e s , a s t u d y w i t h i n t h e E u r o p e a nCommunity was c a r r i e d o u t t o e v a l u a t e t h e r a i n f a l l i n t e n s i t y o v e r someE u r o p e a n s i t e s a s a f u n c t i o n o f t h e s a m p l i n g 1 ime a n d for' v a r i o u so c c u r r e n c e p r o b a b i 11 t ] e s . An empi n c a l f une t i on h a s t n Ы* fourni for' s u c han i n t e n s i t y t h a i p e r m i t ? more a c c u r a t e e s t i m a t i o n of w e t d e p o s i t i o n on tht h e g r o u n d f o r t h o s e E u r o p e a n s i t e s a s s u m e s a s r e f e r e n c e f o r t h o i rс 1 i m a t o l njry . Fi n a l 1 у , a c r i t i c a l a p p l i c a t i on t <> wet d o p a s i t i on e v a l u a t iwi 1 1 bt_- c a r r 4 e d out .

F..N.K.A. - Ucp.PAСНЕ САЯ-АСС1АP О X 24'Ю (nMfifi ПОМЕ ITALY

9 . pURCS DU РМОСПАУМЕ1 8 2

A •_ . . . J

-KF-C-'SSCHE EN COURS-04T PARTIEL rz*.-ZZ;rP&3. A

RAFFC;i7S0UÎ."SrcUR PUBLICATION

- At mosphffi с cii f f usiand depos? i t ion

- bafoty ca lcu lâ t ion=

ITALY IAEA/HPRA/No.11 ITALY IAEA/HPRA/No.11

A ^ L ^ - M I V ] i Г I M>' M< Л М ) * 4 ' Í 4 i'.-M i i Л Л 1 I \ Г ' I Hi ' Г

1 1 Л 1 1 Л Ч I " 'IM 1 AT 1 • N Г К ' ' Ч \ Л П 1 Щ A I H H ' H V

ИЛИ I ' Л С 1 I I 1 1 1 '

Í м . • г < 'Mí t i i - IT

3. AUTtun; пи сме'«сиьидз1> Л . , НЛ1.ПЛ - W \ " f , Í..V.CJ1 V K V I I , I . 4 ' \ ' i Í , Г H . -M'.V Hid

I l i r n i r n i i n t - n t i f i ' - k « f t i i i * - p r n t r t f i m c o m - t

« • x p n - U ! <• , i f 1 i . i l i , m p c p u - i i t m n .

A М Ш М Щ И 1 <l . ( I l " ! • ' ' «- i d \ <•' " i l ' <i t l u - <1(

m i ' i c - i n с т е п ' m< ' h ' H i 1 ^ , J fJ•= f f•nim-nl н ', i nn ; I P < i

f ' . i r j ) i ' i i1*-. ' r a t i o n c h . - i m b i i •- ) .

Л n . i t m n a ' ч ! Г • . . f M i . b . o r г у щ -••! - . . i !

i i i u i w i ! ! b r ( n i l ' i c i l ч и п d u r ! n e m x f \ --,i ; -

• h . ,i - -* - - m . - n i < ' í

K Í 'il(

\ \\A - p,.pt ,рЛ-

ГИ1 ( A-ACí ! -\

OC: _ A.RfCH£hCHE EMCO'JRS-PARTIEL C^^E

i ni''! t \1 • < l l 1 1

" l h t Lrtn-i ot h e fond oli.-i î

t lu i n u r u r f f l c n t j l LiirouL-CLHIIK bai .mci1 in m.in

Î t \ u e o i e

neni intern.il do.s

1'- Bel Ion i , C F . CU'i;iLMUe, S . I)i P i t - t r o , С I m ; r . i o , b . P . S a n t . i r a

4. n'S-jw

Unelemeius l e v e l s to def ine tfie r e t e n t i o n modo J by experiments ! <lat,i colU-rted ondi f fe rent £rotiï>s ûf it.j)i.-m popula t ion . H ib not only gei /cd Che opportunity todetermine the to t a l l eve ls of t race elements considered (Af>, Cr, Lo, Cs, Fu, Fe, Hp,Ni, Rb, Sb, Sc , Sc-, Sn, /.n) in the samples of s ingle foods, complete d i e t s , u r ines ,blood, h a i r s UvniKibli ' d a t . i ) . b"t ni so the s ingle food consumption and the tract 'i-Kme-nts chcnicd! forms which are present in the foods (pa r t of research under s tudy) .In f a c t , t h e chemical forms condi t ion the mel.ibolic des t iny of t race elements .ind itsre ten t ion in man.

LESTRAVAIJK

FNi-A, C o n t i n e n t a l K iwi ron roen t L a b o r a t o r y , C . R . Ï . CasacciaP .Ü .H . 2-iOO - 00)00 Котпа, П л ! \ -

9. OUREE DU РНОСПАММЕ

ос- ... J.../..13WLА • „ J

мЕ ENCO'-'^S-

KATGH7 ZV^VZrCVü f'-BL

Internal Lontami!ManIr.icï fîenientsMet.lbol ÍC h.il.ltu

toо


Development of an Emergency-Use Stack MonitorEnvironmentalStudies.Pathways andMonitoring

3. AUTHOflS 0Я 14VJSTIGATOflS

Kentaro Minami, Hiroyuki Murakami

An exhaust-stack monitor based on a new method has beendeveloped, which enables the easy estimation of the exposure inthe environment in case of reactor accidents. In the new method,the radioactive rare gases at a release source is partly allowedto flew through a limited space, where mounted are two dstectors,one having flat y-ray energy characteristic and the other havingenergy dependency. Accordingly, a 4 л exposure rate due toreleased gas (viR/h-m

2 • 1/h) and an average -y-ray energy o£ the

released mixed radioactive rare gases are measured, thereby pro-viding the exhaust-st&ck monitor with a capability of directlypredicting exposure ratas in the environment.

Japan Atomic Energy Research Institute,Tokai-mura, Naka-gun, Ibaraki-ken, 319-11,Japan.

7. ASSOCIATEC O«GAMtZATIONIS)

9 . PUHATIOMO*

FROM:TO: a/94

- ЙЕ5ЕАЯСН JN

MHÜMITCP QISTHiQUTIOM ПСГОПт

StacK-monitorRadioactive-rare gas.4 it exposure rateAverage y-ray Energy

JAPAN lAEA/HPRA/No.n

1. TITLE ЛМО SUBTITLE

Adsorption of Radioactive Elemental

Iodine Gdj on Incense Stick Aerosol

Environmentalstudies. Pathwaysand Monitoring.

H. Noguchi, M. Murata, S- Kato, H. Matsui, M. Kokubu

Л

To provide basic data for precise assessment of the dose for thepublic cue to radioiodine released from nuclear facilities, theadsorption of radioactive elemental iodine (I

2) gas on incense stick

aerosol was studied.The iodine gas-aerosol mixture was flowed through a cylindrical

glass tube to cause the adsorption reaction. The reaction time wasset by controlling flow rate of the mixture. identification of theradioiodine species was made with a modified Maypack sampler. Thegeometric mean diameter and the geometric standard deviation of theincense stick aerosol were 0.14 grn and 1.75, respectively.

The experimental results showed the adsorption reache

Japan Atomic Energy Research Institute

Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan

7. AÏ-SOCIJ

TO: 3 - / . 8 4

PARTIAL Qtt-&***k R£?OflTW!TH•ед UNLIMITED OISTHIBUTION

Radioiodine

Elemental Iodine

Incense Stick Aerosol

Adsorption

Sticking Probability

JAPAN IAEA/HPRA/No.11 JAPAN IAEA/HPRA/No.11

t . TlTt.5 AMO ÏU«T(Tt.5

>erformance of Silver Alumina Cartridge forSelective Collection of Radioiodine in NuclearAccidents

Knvircnmental 'studies. Pathwaysand Monitoring.

3, AUTHORS ал INVCSTIdATOU

S, Kato, H. Noguchi, M. Murata, H. Matsui, M. Kokubu

To establish the method for selective collection of radioiodir.ein the presence of high concentration noble fission cas in nuclearaccidents, cartridges containing silver impregnated alumina (OD 6Cmm,20ш\ thick) were made in trial. Retention efficiencies of thecartridges for methyl iodide (CH

:.131X) and xenon (

1ЭЗХе) and the

retention ratios (=the ratio of retention efficiency for CH3I to that

for Xe) were examined under practical sampling conditions.The retention efficiencies of the silver alumina cartridges for

methyl iodide decreased from 78 % to 65 % as the relative humidityincreased from 20 %, to 90 % under the conditions of flow rate100 1/tnin, face velocity 85cm/s and sampling tiir.e 60 min. Theretention efficiencies for xenon were < 2x10~

s % under the sane

conditions. The retention ratios were thus more than 106.

These results showed that the silver alumina cartridge could beused for selective collection of radioiodine in the presence of high,concentration noble fission gas under practical sampling conditions.

£. KAMI ANÛ «Alt'MC AOQREXZ O* 0 AS ANIMATION CÛINÛ ÍH= «O"<


Tokai-mura/ Naka-gun, Ibaraki-ken 319-11 Japan

7. А5ДОС1А

FROM:4./.30TO: 3./.85

10.- REScAHCH IN PflO

PARTIAL ОП ПИЛЬ ЯЕРОЙТ WITH iOR UNLIMITSO 0IS7R18UTION - ПСГОПТ

Radioiodine

Selective Collection

Nuclear Accident

Methyl Iodide

Xenon

Silver Alumina Car-

tridge

S. Kato, H. Noguchi, M. Murata, H. Imai, H. Matsui and M. Kokubu :"Selective Collection of Organic Iodide from the Radioactive NobleGas-Containing Atmosphere in Nuclear Reactor Accident," Hoken Butsuri,17, 427 (1982), in Japanese.

j Transfer of ' Co and Cs from soil to plantStudies. Pathways andMonitoring.

Teruhisa Watabe, Hiroshi Kamada

For estimates of the radioactive contamination of plants due to nuclear powerInstallation and world-wide fallout, the transfer of cobalt-60 and caesium-l'J7 fromsoil to plant w s investigated with particular respect to their solubility in soil.A simplified mathematical model was developed and example studies were carried outfor determining the values of the parameters in predictive equations. Thesi;parameters included 'leaching rate1 corresponding to the flux of radioactivityloosed by precipitation from contaminated substances to soil, distribution coefficientof radioactivity between soil particle and soil solution, uptake rate of radioactivityby plant, and so on.

The availability of these nuclides by plant was critically restricted not onlyby low teachability of these nuclides of particulate form, but by the depletion oftheir concentration in soil solution caused by adsorption to soil particle.

The transfer of radioactivity in soil-plant system was most likely influencedby the uptake rate and adsorption capacity of soil among the parameters varyingwith the circumstances under which plants growed.

Teruhisa Watabt?Division of Radioecology,

Laboratory for Radioecology, Nakaminato, NIRS.Tsozaki, 3609, Nakaminato-shi, Ibaraki, 311-12, Japan

Cobalt-60

Caesium-137

Soil-plant system

Uptake

Mathematical model

Science and Technology Agency

Japanese Government

to JAPAN IAEA/HPRA/No.11 JAPAN IAEA/HPRA/No.11

Tritium migration in hydrosphere aroundnuclear facilities

EnvironmentalStudies.tudies.

athways and Monitoring.

In order to know the correlation between the tritium concentrations in r a m water,river water and sea water, tritium concentration in these media has been measuredsince 1977 using a new method for measurement of tritium with direct mixing procedurein a liquid scintillator and the low background ïiquid scintillation counter. Theminimum detection limit for tritium in water was 20 pCi/1 for 500 minutes counting.

The tritium concentration in rain water has been decreasing showing seasonalvariations. The tritium concentration in river water has been decreasing showing noseasonal variations. These data including tritium concentration in sea water aregoing to be analyzed and used to estimate tritium migration in hydrosphere in additionto the data of tritium concentration in air and pine needles around nuclear facilities.

Environmental Research Lab. I IJapan Atomic Energy Research I ns t i t u teTokai-mura, Ibaraki-ken 319-11, Japan

Í Tritiumi Migration in hydrosphere(• Rain water- River wateri Sea waterI Air

Pine needlesLow background liquidscintillation counter

FROM: ..t.. 1978TO: .. /..

TATe OB AOVANCÍMÉNT

5(- RSSsARCH IN ??CG?.STÏAL < М Ш * Х - se.30R7 WITH .

К UNLIMITED OISTRtSUTlON - Hi

H. Amano and A. Kasai "Behavior of Tritium in the Environment (1) Characteristics ofthe Low Background Liquid Scintillation Counter and Prompt Measurement of Tritium inthe Seawater" JAERI-M 8578 (1979)

Radon and its daughters in the atmosphereIVEnvironmental

Studies.Pathways and Monitoring.

A. Kasai, H. Amano, N. Yanase, T. Matsunaga

The concentration of raàon and its daughters in air was measured at the same time

n i v c кцч I i iur i л и п а з шаис i~ i c u t • r i i a u t i n - i c i u i . i

don and the barometric pressure in closed cave wasand its daughters, Uie dU abetween the concentration of ra

Environmental Research Lab. IIJapan Atomic Energy Research InstituteTokai-mura, Ibaraki-ken 319-11, Japan

RadonRadon daughtersConcentration in a i rEquilibrium stateInternal exposure doseLiquid s c i n t i l ï a t o rPortable Ge detectorBarometric pressure

FROM . . / .1979TO: . . / . .

H. Amano and A. Kasai "Measurement of Rn-2?2 in Air Using Liquid ScintillationTechniques", RADIÜISÜT0?ES,3Q,649(í98í)


Vertical distribution of radionuclides in the sea sedimentoff the coast of Tokai-mura, Japan

EnvironmentalStudies.Pathways and Monitoring.

A. Kasai, N. Yanase, K. Sekine

Sea sediment cores were sampled at 13 different points off the coast of Tokai-mura (7 стф, 70 cm depth). The sampling area was about 5 km along the coast lineand about 2 km from the coast to the open sea. Core samples were cut in slices 5cm thick each, and the vertical distribution of grain size and radioactivity «eremeasured.

Distribution of a radionuclide at each sampling point was fairly different.In the sediments near the estuary of the Kuoi River T3'Cs was detected, but it wasnot detected at points far from the estuary. Distribution of 4ÜK was fairly constant,while the daughters of " S U and г з г

Гп showed considerable change of radioactivityvertically and horizontally, both in the same pattern.

It was supposed that sea sediment down to one meter depth was considerably

disturbed and the 37 r supplied by Kuji River was accumulated near the estuary.There was no obvious correlation between grain size and radionuclide concentration.Most sea sediments mainly contained the sand hairing the grain size from 0.074 to0.12 mm. Main elements in the sea sediments were Si, Al, Ca, K, Na, Fe, Mg and Ti.Investigation will be made, on the behavior of radionuclides in sea sediments byanalyzing the correlation between content of stable element, grain size and radio-nuclide concentration.

Environmental Research Lab. II

Japan Atomic Energy Research institute

Tokai-mura, Ibaraki-lien 319-11, Japan

FROM:../.. 1978TO: . ./ . . 1937

mXJSOeX- ЯЕ:=АЯСН IN ?ЯОСЯ£53 _шюттшшхмшшшшш!».даытшхшшшнвдхшюшх

Vertical distribution ofradionuclides

Sea sediment

w

Measurement of Fallout and Dose Estimation in Tokai-murs

IV

EnvironmentalStudies. !Pathways and Monitoring. í

A. Kasai, T. lmai, K. Sekine, T. Matsunaga

4. ASST=...=T

The concentration of fallout nuclides in air has been measured since 1962. Falloutin air was collected monthly by passing air through a f i l te r paper in Tokai-mura. Thedetermination of gamma nuclides on the f i l t e r was carried out by т-гау spectrometryusing GeiLi) detector, and that of plutonium was carried out by «-spectrometry afterchemical separation.

The dose commitments to man through the year 2000 due to inhalation of the239,240pu in air were calculated from the data obtained in accordance with the 1CRPlung dynamics model.

Environmental Research Lab. I IJapan Atomic Energy Research InstituteTokai-mura, Ibaraki-ken 319-11, Japan

9. ОЦЯАТ1О« О*

глои-...i.. 1962TO. . . / . . SUBMITTED FOH PUBLICATION

Fallout

Dose

A. Kasai, T. lmai and K. Sekine "Measurement of Fallout and Dose Estimation for 239,240pt

in Tokai-mura, Japan", Health Ph>sics, in press.


*. AÍS71ACT

i " h o o i L - r n t i U i f u " c U o n s i ' . T j j . - T î r . " - - i w t _ > - v ^ P - i ':; f :< : - . ) : . : к - - _ : >: ) o i .. x i - , t . 1 1 1 i l . o i . ' i " l u L T c r : : h i v ^ : • • > : , i " ' " r , i - • " • , i V . " ' r n .-;•";• : f ! j yj: •••::.•• <i i î ' r . f ' i M D ' Î.».' С t r i o ; ' i o t h o < : . Th-"1 i t : - ) Г . - ' - т . • f f r i t j o r i v - 1 . t h - 1 ,•; г . " . . ii . r v c t l y f t - »« ч p . l . ; p - h - 4 r , h t . u ; •;' ' г .": л ' Ц - h , . - . - : ! • i n m . 1 ; . ^ , h . i . ; !,•-•:. ' i

- u ; o n e o i ' t h e u s c t ' - i l i ) . ; : : i . o l n c : - - t h > : : : :• !• - i v: ' n. i- V ) у , f y г , p i ; - i : , .t h t 1 r ' f l i n t i l o - _ T . ' T ( - * y r - i ' T , * 1 ' M " i h - H E ) Í * : P I ' . . J * . Í ; - ' Í if. Л . T .:, :; I i - t i t " ! .•: > c c • t . ' o i ' i ' t . n c i - T . ' . r r i ( . i " - t í - n - ч * r* !••-;:[>•. .-•• k i ' . - t . l h - i r * - : ; - - ' t v c ' * * i r .i t •',}.;.-,! I-1 •• *•'.. ^ v ' i l j / j t ' 4 ' - h t ! >.;•' .:• ' 1 * > • , . - r ' f i n : - * n 1 ' Г о с . к : t i •_• ! ; ; - 1 у .

' h O a i - l i O c i - " 1 Î M J f I ' l J t T l L i i i . '. •". .• ; ; ' > : " ' T . . " C . * h >V- : ' i * r ! iT> 1 л 1 . * ' 1 ' ii ' * i ! ' l o " ! v l . ' r i j í . ; : ' : r n i : v ' : ; o i ' i ' 3 ' : , : : ' ' . • ' . ; . v . J ' . •-• ; : ' • < " • • : ir1** ..'. • • : < : • , ' • . : "

i - l ' » ; - t f i ! ' ' f t . h o o v ; i l j - i t . ' - n " ' Г i .••• - ; ; ' : ' • > - • _ .• ;• r- - " : } ! . , r - : - • : . M

F R O M : . . / ] , < - 2T O : . . / J . . Л

Î - RESEARCH IN ?HQGfl£S5 -PARTIAL ОЯ/ÇfNAt.- RË'QRT WIW Z.JMVÏS6Й UNUMÏtÈO'OlSTRIBUTION - i f i l íB f i» '


4 . A S S T B * C T

\ M ' i ! " - i - r . y л j r v - ; s 7 H t r _ " - .-;,:..: _i h - * I i c o p u . - " h . i d - - - Ч ! l-*v -1 •; •_ 1 .:. - ,,. J i - v . - . " : f

j * j i - Ï I ^ V r - i J . . ^ - s >i : J i ! £ D ' s r v . ' i ] ! - 1 : - ; - - г « > г т - , Г з ' t ^ " h e h v l . t , > ; ' 1 - - г Ь ч i*_-1•л: . i r w r . t . s , - î t i J : - M : i - c > T : . Г . , ••, - ; : \ . t > . ( _ ' r > : : - :- i , ; , i - - : ' t - _ - ! - j ^ j ! t- , J I ,c i i *> :

[ • J L . - J U I " L I C / , T / 4 - , : !•••/•'! f i ; - - w , , r / h ) т l M г 1 Г - / h , Ü . Í ILJ >, L M L . t - x p . :, , n !•."-•

л - Ч * r .'•- i i i î " D i V v ' r : ; : ^ 1 •:.• r t v : > - v 1 : о : :• ,••./;•!. ; ' > " , h - i i f - b f i , i n - Г 1 1 -.ii- .

;• ! •••:•,-"•• ; - • .' •••;•.•" - г - .• : : с * :•. ' : • _ , - . : . . . ' - - . • : г ; ; •• : ' - .. \ i

• h i . : •... r v . ! . с J : 1 .( •• j . . - . ; . м * . - : ' , • > ; • , " • • ' : ' ' ч - ••• r 1 , - - • , } •• j i r o : " - . ; , > .

••-• . г . , 1 : м г . . ' 1 - ^

FROM- А / . í ••TO: ._ ) / . ] .

Effi UNLIMITED DISTRIBUTION -


M. Chmo. H. Ishik2W2, M. Kai, К. Аза:, Y. Закатига, 5.

The сое*? зуосеп ЗР ЕРГ has been cevelopei for preaicti-из: the uoso to tne pi:ol_c

frcn a plume releases in a nuclear ac~iaer.t. Seme operational tests have seen

coraucted to imorovea the cede system. The sequential calculations 3f ;r_rr. f ieic,

concentration and dose distrioution in the local (-25 '<~i) or regional (-100 kx.i

scales are carried out by using a conversational тшее sf the code systern. This

code system has the tooogrschicai data s round a l l the nuclear sites n Japan.

By using those data a user zan display the calculated resj i ta, sue1, ac wr,c fieia,

concentration and dose distribution isooieths and c-ur.terreas'jre зге-, ^raonically

an the ;пар according to his order. The calculated results as well as the s i te

characteristic, meteoro logical ar.d toporrapnical data preoarea for tne calculation

ar» recorded in the same form of the data-pool system, wnicn was aeveloçec m JAEP1,

i"i orocr to be treated with esse. Si;се э calcji^ti^n "oael is aealt vith ip.ce e-.'M—,

or" the cede system, i t is rather sasy to sxenar^s а тосе! fer зг. i"provei one.

Jaoan Atomic Energy пезезгеп Inst i tute,

Environmental Researcn L^.cora^ory I

Tokai-Tiura, Nato-gun, Ibar=ki-'-:en, Japan.

F R O M : . . / . . l g S 0TO: . . / , . 1 9 Q 5

?.Kflï2CTÎ- RSSEAflCH IN ?ROG3E£S -PARTIAL OR FINAL RsFORTWITH LIMITEDOR UNLIMITcO DISTRIBUTION -"№£*&№

cede-sys^en

nuclear zc-ice

wine f iela

concentration

acse

aata-pooi

1) M. Taoei and Y. Naksmura, A Software for Transforma:ion ar.c Map Drawing

Numerical Informations tor Lar.c. JAESI-M 32-QM (19c2)

CF ССМЯЯЕЗ? COCES FORTHE REALISTIC SIMULATION OF

ATMCKPUKRIC DIFbUSICN OVER CGMPL£:i TERRAIN

- Mv i г -гтски"

r'aLhvjys jmi Ti'-ч

M Chino. Il Ishikawa. M Kai. S Monuchi

In oraer to calculate the «tmosphenc transport and diffusion of rad 1 oa<_t:VP

nuclides over complex t e a m , several computer codes have be- n developed T!v

code. WIND 04. produces the three dimensional mass consistent vind field

including topography, using the observed wine data The code. CGARA. is

;rformed in JAERÍsince 1980. A comDuter code, which cajculates externa] dose from anydistribution of radioactive nuclides. has also been developed

JAPAN ATOMIC ENERGY RESEARCH INSTITUTETOKAI RESEARCH ESTABLISHMENT

TOKAI MURA. NAKA GUN. IBARAKI KEN. JAPAN

F4OM: . . / . . î } z 0TO: . . / . . Г - /

*£nTlAL QR F'HAL Д£=СЛ Г WiTrí LlWOR UNLIMITED 0IS7RI3UT1ON - ^Xftffl

computer codeairbone effluentwlnd fielddiffusiont.-xtern.il dose ,complex terrain

1 Chino.M .Computer Code COARA by Particle In-Cell Model for AtmosphericDiffusion of Gaseous Waste. JAERI M 82 219 1S83

t! Chino.M ,Atmospheric Dispersion Model by DPRW Di&crete Particle Random. Walk Method, JAFRI M 63-0&1 1983

3 ishikawa.h..A computer code which calculates three dimensional mays

...consistent wind field. JAERI-M 8 3 - П З 1983

гоOs


1. TITLE ANO SUBTITLE

Performance of Silver Alumina Cartridge forSelective Collection of Radioiodine in NuclearAccidents

Environmental ' ___studies. Pathwaysand Monitoring.

S. Kato, H. Noguchi, M. Murata, H- Matsui, M. Kokubu

i . Л13ТЯЛСТ

To establish the method for selective collection of radioiodinein the presence of high concentration noble fission gas in nuclearaccidents, cartridges containing silver impreanated alumina (OD 60mm,20mm thick) were made in t r i a l . Retention efficiencies of thecartridqes for methyl iodide (CH, P I I) and xenon (13-Xe) and theretention ratios (=the ratio of retention efficiency for CH3I to thatfor Xe) were examined under practical samplinq conditions.

The retention efficiencies of the silver alumina cartridqes formethyl iodide decreased from 78 % to 65 % as the relative humidityincreased from 20 % to 90 % under the conditions of flow rate100 1/min, face velocity 85cm/s and sampling time 60 min. Theretention efficiencies for xenon were -- 2x10 ~ s % under the sameconditions. The retention ratios were thus more than 106.

These results showed that the silver alumina cartridge could beused for selective collection of radioiodine in the presence of highconcentration noble fission aas under practical samplinq conditions.

Japan Atomic Energy Research I n s t i t u t e

Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan

7. ASSOCIA.T3O OA

FROM:4./.80TO: 3./.85

10. STATÉOf ADVANCÎM6NTPflOJGCT •- RESEARCH IN PROGRESS -PARTIAL. ОЯ f lNAL REPORT WITH UMlTEPOR UNLIMITED DISTRIBUTIONOUOMITTCD ГОП PUBLICATION

5. oesc^t^To-s ол к*- «c^as

Radioiodine

Selective Collection

Nuclear Accident

Methvl Iodide

Xenon

Silver Aluirina Car-

tridge

S- Kato, H. Noquchi, M. Murata, H. Imai, H. Matsui and M. Kokubu :"Selective Collection of Organic Iodide from the Radioactive NobleGas-Containing Atmosphere in Nuclear Reactor Accident," Hoken Putsuri,Г7, 427 (1982), in Japanese.


Adsorption of Radioactive Elemental

Iodine Gas on Incense Stick Aerosol

Environmentalstudies. Pathwaysand Monitoring.

3. AUTHOHS ОЯ INVESTIGATORS

H. Noquchi, M. Murata, P. Kato, H. Matsui, M. Kokubu

To orovide basic data for precise assessment of the dose for thepublic due to radioiodine released from nuclear Facilities, theadsorption of radioactive elemental iodine (I?) gas on incense stickaerosol was studied.

The iodine gas-ajrosol mixture was flowed throuah a cylindricalglass tube to cause the adsorption reaction. The reaction time wasset by controllinq flow rate o* the mixture. Identification of theradioiodine species was made with a modified Maypack sampler. Theqeometric mean diameter and the geometric standard deviation of theincense stick aerosol were 0.14 i.m and 1.75, respectively.

The experimental results showed the adsorption reached anequilibrium in about two minutes. The adsorbed fraction dependedlargely on the initial iodine concentration above 10~

! ] g/cm\ but

the fraction was almost constant, about 25 ?, below this concen-tration. The stickinq probability in the present reaction wasestimated to be about \Ъ~

7 . A semi-emDirical equation for esti-

mation of the adsorption was developed, taking into considerationthe term of desorption of iodine from the aerosol . The calculatedresults by this equation are in good agreement with the experimentalones .


Tokai-mura, Naka-aun, Ibaraki-ken 319-11, Japan

FROM:6./.8n

TO: З.Л84

10. ST*:EQ*= AOVÍNCEMENTPnOjCO^- RESEARCH IN PflOGSESS -PARTIAL Gfl-PIMAL RE30flT WITH LtMlTEO-©ft UNLIMITED OlSTRiaUTION — -ЯЕтЮПТ-

Padioiodine

Elemental iodine

Incense Stick Aerosol

Adsorption

Sticking Probability

JAPAN IAEA/HPRA/No.11 MALAYSIA IAEA/HPRA/No.11

1. TITtE AND SUBTITLE

Development of an emergency-Use Stack Moni toc

2. *HOAD HEADING

EnvironmentalStudies.Pathways andMonitor ing

3. AUTHOffS ОП INVESTIGATORS

Kentaro Minami, Hiroyuki Murakami

4. AtSTRACT

An exhaust-stack monitor based on a new metdeveloped» which enables the easy estimation ofthe environment in case of reactor accidents. Ithe radioactive rare gases at a release source ito flow through a limited space, where mounted aone having flat -у~

гаУ energy characteristic and

energy dependency. Accordingly, a 4 тт exposurereleased gas (viR/h-m

2 • 1/h) and an average v-ray

released mixed radioactive rare gases are measurviding the exhaust-stack monitor with a capabilipredicting exposure rates in the environment.

hod has beenthe exposure inn the new method,s partly allowedre two detectors,the other havingrate due toenergy of theed, thereby pro-ty of directly

Japan Atomic Energy Research Institute,Tokai-mura, Naka-gun, Ibaraki-ken, 319-11,Japan.

FROM: 6./8ÛTO: 3-/84

- RESEARCH IN PROGRESS -On КИМ. ncnOnTWfPH LIMfTCP

Stack-monitorRadioactive-гare gas4 n exposure rateAverage у"~

гаУ Energy

J

1 TiTLF AMD S-BTITLE 2 ВНОДП HFADING


Shcir 11 i n H a r l l a n \ i d i r t

4 AD5TRACT

i n n r p f l r t i i i i l a t p - - w h i r h Ьлс1 been t o ] l e i r o d bv h i g h - v o t u m

5. NAME AND MAILING ADDRESS OF ORGANIZATION DO'NG T H E WORK

D r . s h a r i ï a h H . i r l i a n A id ic iticprfrriTK'nr o ! Pin s u sF j r u l U ot I ' h v s n a l 4 A p p l i o ' l ч к - ш о

S SPONSORING ORGANIZATIONS

The Sal ion,i] Uni verw

9 DURATION Of

PROGRAMME

FROM 1 4 !TO \Z Hr;

I . ... > , , , _

JRfKXECT RESEARCH IN PROGRESS -

, Нл, 1 л , ... bm .mil t u

эп a n a l y s i s ( I S W l . P l a n t s

l e d с1(.,эт1-,иг i-nvirnnmcnr -

Ai г - p . i r l l e u l a i оь

] n s l r u m e n t a ) noиart l vat i on an,) 1 %

П l l f i m - n t a i ( . o n c i M i t vAt i o n s i n t n v i r o n m e n t a l R t ' i c r t n c c M a t e r i a l - K l v

S h r t r i f . i h P d r h a i i A i d t d . B u l l f f i n ul t h e I n s n t u f c o f P h y s i c s

Ma 1.1 V4 i a , v c l . (*, N n . 2 , l l ) 8 i . 5 1 - " i ò -

00MEXICO IAEA/HPRA/No.11

Implementation del Programa Preoperacional de Mo-

ni toreo Ambiental en l a Planta Nucleoeléctr ica de

Laguna Verde.

IV

ESTÚDIOSAMBIENTALES

Valdovinos M.A., S i lva H, A. , Cantú T. A.

4. RESUMEN Qomo pQTf0 de Xos requis i tos para obtener l a l i cenc ia de operación

de Id planta Nucleoeléctr ica de Laguna Verde, se ha implementado un Progra

ma de Monitoreo Ambiental Preoperacional. El diseno dei mismo se basó en -

Ios estúdios prévios dei médio ambiente (meteorológicos, h id ro lóg icos , eco

lóg icos , demográficos, e t c . ) y en l a evaluación de las dosis po tenc ia les , -

que de ocuerdo a ios modelos u t i l i z a d o s , r e c i b i r á l a población a través de

las d i ferentes rutas de exposición. Para la implementación del Programa se

construyó un Laboratório denominado de Monitoreo y Dosimetría Ambiental —

que se l oca l i za a 13 km a l Sur de Ia Planta Nucleoeléctr ica,en e l que se -

efectúan ias act iv idades relacionadas con e l Programa (recolección y p repa_

ración de muestras, aná l i s i s rad io lóg icos, radioquimicos, químicos y bioló^

g icos) . El monitoreo ambiental,está respaldado por un Programa de Garantia

de Câlidad que incluye Procedimientos de Laboratór io, Muestras de Intercom

paración, Pruebas de ve r i f i cac ión de funcionamiento de equipos y Control -

de documentos.

'. NOMBRE V SESlAS DE LA ORGANIZACION QUE REALIZA EL TRABAJOComisión Federal de Electricidad.Proyecto Nucleoeléctrico Laguna Verde.Ingenieria Ambiental.Apdo. Postal № 53.91680 Cd. СагсЫ, Veracruz. MEXICO.

Comisión Federal de Electricidad.

AC'ON DEL PROGRAMA

1 / 81Ï2 / 8 5

10. 4ITUACIONPROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O NO LIMITADA -INFORME PRESENTADO PARA PUBLICACION

Monitoreo y Dosime--tría Ambiental.

RadiactividadAmbiental.

Ingénierie Ambiental. Sección 4.1,5 Monitoreo Radiológico del InformeAmbiental de la Planta Nucleo^-tp-trica Laguna Verde. 122 páginas más ta-blas y figuras. Publicado en 1982. Comisión Federal de Electricidad.

NETHERLANDS IAEA/HPRA/No.11

Uptake and retention nl rad wnui 1 ides by marine urgani

Polonium- 2 10 and trace-elements in (deep)-sea orgdni sin

ENVIRONMENTALSTUDIES

A.W.v.in Ueers

ABSTRACT

Л study is made of the occurrence of the natural alpha-emitter polonium-210 in deep-sea organisms and organisms from shal low-water in order to assess and comp.ire therange and variation of the natural rjdi.itii>n dose received by these organisms fromdifferent habitants. The analyses are perfumed using wet digestion, spont.ineüusdeposition of polonium on nickel plates and alptia-spectrometry. Polonium-210 isused ,i<; a yield tracer. TÎÎG studv comprise'; л1чо the distribution of polonium-210within the organisms.

A study of the occurrence of trjie-elements in organisms from the deep-sea andfrom shallow water is carried out using neut ron-at-t i vatíon analysis. The resultswill be used to assess the potential for .it-cumulation of man-made radio-isotopesof these elements by deep-кел organisms in comparison with organisms from shallowwaters.

NAME AND MAILI*4Ci AQO^ESSOF ORGANIZAI ION DOING ТнЕ WOB

Netherlands Energy Research foundalion (ECN)

P.O.Box 1, 1755 ZG Petten, The Netherlands

,TED ORGANIZA

SPONSORING ORGAf.l?ATIONfSi

FROM. \4tii10 1986

10 STATE OF ADVANCEMENTRHOJEKK- RESEARCH IN PROGRESS-

6 DESCHIPTQPS OH KEV V

r.idionucl idesmetabolismmarine organismstrace-elementspoloniumradiation exposure

NETHERLANDS IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

to

Internat irradiât ion by Jerosо1-attached radon- <md choron-

daugluers from building materials.

2 0ЯОДО HEADING

ENVIRONMENTALSTUDILS

3 ftuTHORS ОЙ INVEST!

Scoute,J.R.D.

ABSTRACT

The behaviour or radon- and thoron-daughter products and their adsorption on aerosolsis studied. This adsorption can play a significant role in the lung exposure t« radia-tion from inhalation.

An alternative method of aerosol particle selection makes use of an aerosol centri-fuge, where the particles are deposited on a lonj; metal tape. The fie nos i г on thetape can then be analyzed for alpha-radioactivity per aerosol particle size interval.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE VvORK

Netherlands Energy Research Foundation (ECN)P.O.Box 1, 1755 ZG Pet ten, The Netherlands

SPONSORING ORG

9. OURATION OFPROGRAMME

FROM. . . M . 9 8 JTO. . ./-1^84

10K- RESEARCH IN PROGRESS -

Шмишшюжакккшикк

6 DESCRIPTORS ОН <Ё

lungdoseradon-daughtersthoron-daughtersaerosolindoor exposureparticle s ize

1 TITLE AND SUBTITLE

T r a n s p o r t b i j g r o u n i i w a t ' T 'if r a d i o n u c l i J o s

2 BROAD HEADING

Environment.л 1 StudiesPathways ann Mniutonn-j

3 AUTHORS OR INVESTI GATOHS P. Glasbergen, J. van der Vorst

The aim of this study is to estimate the? underground travel patterns and displacem^n

in highly .saline waters of radionuclides released from a salt dome repository of radio-

active wa^te. Transport through a number of aquifers and semi.-pervious strata will he

studied with help of a three dimensional computer model. Density flcjw( temperature

distribution, inhomogeneities and sorption will be taken into account. The spatial

variability of the composition of the underground will D P studied by runninn the model

for a broad range of input data. The model must lead to a description of tht surface

area potentially effected-

NAME AND MAILING ADDRESS OF ORGANIZATION DOi

Rijksinstituut voor Drinkwatervoorzi

Postbox 150

226Q AD LEIDSCHENDAM

ТГЕ NETHERLANDS

SPONSORING ORGAN JZATIOfufS>

Commission of the European Communitieb

FROM 5 63

TO 12.BJ

- RESEARCH IN PROGRESS-

pathways

modelling

groundwate

ыо

NORWAY IAEA/HPRA/No.11 PAKISTAN IAEA/HPRA/No.11

TITLE AND SUBTITLE

Radioactive fallout measurements

2 BROAD HEADING

Environmentalstudies. Pathwaysand Monitoring


Christensen, Gordon C. and Sab0, Arne

4. А05ТЯДСТ

Samples of precipitation. air and milk from four stationsid and mecothers)-

in Norway are regularly collected and measured for falloutradioactivity ( i 3 7 Cs, 1 3 1 I and

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE IVOR.

Institute for Energy TechnologyP.O. Box 4 0N-2007 Kjeller Norway

The Norwegian Defence Research Establishment


9. DURATION OP

FROM- . . /T O 6 . . / . . 8 2

RESEARCH IN PROGRESS-

Я&ШАкй53йййШНШ

terrestrial environmenradioactive falloutradiocesiumradioiodineairprecipitationmilk

Environmental Radiological Surveillance

Sub - Title : Monitoring of radio-activity in theenvironment/human food chains

Environmental Studies.Pathways and Monitoring

Author for correspondence. д ^ ^ д ^ P e r v e e n # N p § Faruq, M.U., Afsar, M.,

Afzal, M., Haq, Ehsanul,, Afghani, Ihsanullah, Shamim,M.

ABSTRACT

The programme of the radiological monitoring of the environmental media andthe items of diet of the population as reported in the last Health Physics Research Abstractswere continued. The environmental media selected for the radio-isotopic analyses were air,precipitation, surface and ground water, vegetation etc. Typical items of diet included inthe radiometric analyses wer-? seasonal vegetables, various meats, wheat and cereals etc.

The regime of analyses included gamma spectrometry of the samples on acomputer based Ge(Li) detector gamma spectrometer followed by the radiochemical analysesof the ashed samples for the separation and measurement of the radionuclides of radio-logical significance to the population particularly Sr 90 & Cs 137.

The radionuclides present at low concentrations in the environment atPINSTECF during 1482 were Ru 106, Ce 144, Be 7, К 40, Cs 137, Hg 203, Sr 9O,jCr 51Ag 110m etc.

Détermination of Sr 90 in human nones was also carried out in order to studythe transfer of radionuclide of long effectif e half life from the environment to man.

M LING ADDRESS OP ORGA DOING THE WORK

Pakistan Institute of Nuclear Science & Technology'(PINSTECH), P.Ü. Nilore, Rawalpindi (PAKISTAN).

Pakistan Atomic Energy Commtssiun(PAEC).

rfiOM ' 76TO 12 ЯЗ (contei)

10PROJECT - RESEARCH IN PROGRESS -PARTIAL OCFINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

6. DESCRIPTORS OR KEY WOR:

EnvironmentRadiological MonitoringAir,PrecipitationSurface waterItems of diet.

Abdul Azu, Ninhal Perveen, M. Afzal, Assessment of Transfer Co-efflcienl from Dietto Human liune for the Environmental Sr 40, - IAEA-SR-85/54. Paper tu be presented atthe Seminar on the Environmental Transfer to Man of Radionuclides Released from theNuclear Installations, 17 21 Oct. 1ЧКЗ in Brussels, Belgium.

POLAND IAEA/HPRA/No.11 SOUTH AFRICA IAEA/HPRA/No.11

??E METHOD OF PRODUCTION OF THE SYNTHETIC

LOCAL RADIOACTIVE FALL-OUT

2. IMOAO «СЛЗ ЧС I

Environmental^Studies.

Krzysztof Uarnowiecki, Danuta Garus

The Laboratory method of producing the local radioactive

fall-out material h^s been developed. The composition and physico-

chemical properties of the material obtained are very similar to

those of fall-out material from nearby surface nuclear explosion.

The fission products are created during a neutron irradiation of

melted sand grains containing uranium. The synthetic material is

used for biological, agroteehnieal and decontamination experimental

studies.

Central Laboratory for Radiological

Protection, 0 }

_1 9 4

.( a r s z a w a i P o l a n d

8. SPONSORING OA£ANIIATION<S1

State Agency for Atomic Energy,Poland

9. OUHA3*tQN Of

F«OM: . . / . .то. .. : «1

STATE O« «BVMCEuEN

! SUBMITTED я

n icelar explosion

radioactive fall-out


11 Ж'ЕЯЕмСЕЗ O« •tCENÍ-^uei.lCiTi 1E1.S ISSUES f l lOU THt

K.Zarnowiecki, D.Garus: The method of production of the syntheticlocal radioactive fall-out. :!ukleonika, vol.26, 4/6 /1981/.

ASSESSMENT ÜF COU.ECTIVK DOSKS DUh TO RADOK RELEASES FROMMINING OPERATIONS IN THE WITWATERSRAND AREA

ENVIRONMENTALSTUDIES. PATHWAYSAND MONITOKINC

VAN AS, D; BKITS, R J N; GRUNDLING, Ai REDDING, SUSAK.

Airborne radiometric data were utilized to quantify tht1 ' ? 6Ra content of morethan 250 tailings dams spread over 100 km alona the Main Reef. Methods formeasuring radon emanation from these dams were developed, while ambient radonconcentrations are measured with passive radon monitors.

A source term has been defined and is used with the AIRDOS and VALLEY codesto predict radon concentrations from these enhanced sources. Model predictionsare verified by field measurements.

From the annual average radon concentration and the population distribution,the collective doses will be determined.

NO MAILING ADD ESS OF OBGA

NUCLEAR DEVELOPMENT CORPORATION OF SOUTH AFRICA (РТУ) LTI

PRIVATE BAG X256

PRETORLA

0001 SOUTH AFRICA

7 ASSOCIATED ORGAl

8. SPONSORING ORGANIZA

FROM 6 ' 81TO 6./ Ш

10 STATE OF ADVANCEMИКШИСТ - RESEARCH IN PROGRESS -

TAILINGS

NATURAL RADIOACTIVITY

RADIUM-226

RAD0N-222

EMANOMETERS

ыto

SOUTH AFRICA IAEA/HPRA/No.11 THAILAND IAEA/HPRA/No.11

TITLE AND SUBTITLE

BEHAVIOUR OF RADIUM AND ITS PROGENY IN THE ENVIRONMENT

«ОАО HEADING

ENVIRONMENTAL

STUDIES, PATHWAYS AND

MONITORING

DE .JESUS, A S M ; VAN AS, I); BRITS, R J N and WOOD, S.

Gold/uranium mining in the Witwatersrand has led to enhanced concentrations of? 2 G

Ra and its progeny in localised sites, namely the t-iflings impoundments.

The behaviour of radium in the impoundments,and its migration and distribution

in surface and underground waters,are under investigation. Radium mobility, as

deduced from partition functions determined from in situ measurements, is compared

with the mobility measured in laboratory experiments. The medium-terni migration

of radium in soil is evaluated from 225

Ra profiles carried out on the original

soil underlying 60-year old tailings impoundments. Attempts are made at sper.iation

of radium in the impoundments.

5. NAME ANU MAILING A00RÊSSOF ORGANIZATION DOING T H E WORK

NUCLEAR DEVELOPMENT CORPORATION OF SOUTH AFRICA (PTY) LTDPRIVATE BAG X256PRETORIA0001 SOUTH AFRICA

7. ASSOCIATED ORGANIZATIONtS)

8 SPONSOHING ORGANIZATIONS!


FROM 6 , 7 8TO Í 2 / 8 3

10 STATE OF ADVANCEMENTRESEARCH IN PROGRESS

шк1июнгаа«(яткшххшпшюкмше

RADIUM-226

RADOK-222

RADIOKUCMDE MIGRATION

RADIATION MONITORING

fcnvironmental R a d i o a c t i v i t y Monitoring f o r RadiationP r o t e c t i o n of Office of Atomic Energy for Peace

? ВРОЛИ HfcAOtNG

Environmental Studies

Prempirakul ,11; Biramontri ,S; Milintawisamai,M.

Polphong.p, Mahapanyawong.S; Rativanich.N.

The work on environmental radioactivity monitoring has been a continuing activity

of the Radiation Measurement Division since the year 1961,The conducted work consisted

of the measurement of gross beta radioactivity and the determination of strontium-90

and ceasium-137 on various samples such as air,water, rain water, fallout,, soil,

grass, vegetable and some types of meat. Samples were collected from various locations

covered all regions of the country. The results were evaluated to епьите the safety

of public and personnels of Office of Atomic Energy for Peace from radiation hazard

due to the testing of atomic bombs in atmosphere and the operation of the research

reactor ( TRR-1)_, The results showei that level of radoactivity in the investigated

samples were within safety limit.

Radiation Measurement Division


Bangkhen, Bangkok 10900, Thailand

Office of Atomic I'nergy for Peace


FROMiSbl Continuing

TO

10PROJECT RESEARCH IN PROGRESSPARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED POR PUBLICATION

Environmental Radio-activity MonitoringCross Beta RadioactivityStrontium-90

Ceasium-137

11 RE. FF HE Nets OF ПЕСЕ\Т PUBLICAI

0Л1Р Annual Report 1У8Л

THAILAND IAEA/HPRA/No.11 THAILAND lAEA/HPRA/No.n

The determination of plutonium in cnvironecntal samples.

VÉS14GATORS

CHITTAPORN, F.

The determination of plutonium in s o i l , fresh water, and a i r in cen t ra lpart of Thailand has been car r ied out . The plutonium in the samples andplutonium-2**3 t racer arc separated by e i t h e r a solvent extract ion or an amionexchange. Final ly the plutonium is coprccipitafccd with cercoushydroxidc andf i l t e r out on f ioter paper and moasuroed by alpha spectromctry.

Health Physics DivisionOffice of Atomic Energy ft>r PeaceTlbinon Vibhavadi-RangsitBanfíkhen, Bangkok 10900, Thailand

7 ASSOCIATED ОПОА

FROM 10, 1982то 09 1986

Research in progress10 STATfc OF ADVANCEMENT

PROJECT RESEARCH IN PROGRESSPARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION- REPORTSUBMITTED FOR PUBLICATION

PlutoniumEnvironmental samplesSolvent extractionanion exchangeeoprecipitated with

ceroushydroxidoFilterAlpha spectromctry

The measurements of radon, ttioron ind their daughterproducts at dif

rercnt locations in Thailand.

CHITTAFORN, P.

The objective of this study is to continuou* measure both indoor andoutdoor radon, thoron and occasionally monitor their daughtor products, SaA» RaE,RaC, Th8 and ThC at four stations in the central, the northern, the southern, andthe northeastern part of Thailand. The results of thceo measurements will providebasic data of considerable scientific value in establishing potential hazards andin providing basic geophysical measurements. Also it will provide data useful forworldwide comparisons.

5 NA"u1f AND M A I L I N G ADDRESS O' ORGAMZATiO*. DOi'

tie a l t h Physics Div i s ionOffice of Atomic Energy f s r PeaceThanon Vibhavadi-3angsit3angkhen, Bangkok 10900THAILAND

PROGRAMME

FROM 10 I 9 8 Iто 09 1986

Research in progress10 STATP Qt H D V A N C E M E N T

PROJECT RESEARCH IN PROGRESSPARTIAL OR FINAL REPORTWITH LIMITEDOR UNLIMITED DISTRIBUTION REPORTSUBMITTED FOR PUBLICATION

KE v WORDS

Continuous measure

RadonThoronOccasionally monitorDaughter productsScientif ic ValueGeophysical meaeurementaWorldwide comparisons


"Environmental Protection, Support and Assistance"

2.IV

Environmental

Studies -Pathway and Monitoring


R.F.. Jaquish, J.I1. Corley

ABSTRACT

This study is designed to provide technical support to the US Department of Energy(DOE) in the area of environmental safety and health. The study utilizes themultldísciplínary expertise of Laboratory staff to conduct studies in support ofDOE's environmental protection responsibilities. These studies enable DOE torespond in a timely and knowledgeable manner to a variety of issues on health,safety, and environmental protection. The work has historically been in twoareas: impact analyses and guide writing. Analyses of the impact ot proposedstandards, regulations and administrative requirements is a service providedon an as-needed basis. Review and development of effluent, environmental andground-water surveillance methods and reporting procedures are continually beingprovided to DOE. In addition» speci"! studies are undertaken at the requestof DOE to meet unanticipated or high-priority needs. The study also coordinatesresponses from other DOE contractor and field offices and organizes technicalconferences and workshops for DOE and contractor staff.

5. NAME ANO MAILING ADDRESS OF ORGANIZATION DOING THE WORK

Battelle Northwest

P.O. Box 999

Richland, WA 993Ь2

USA



US DOE

DURATION OFPROGRAMME

FROM. . 6/B.OTO ../Continuing


т#тШДОШ№>№№Ш№

DESCRIPTORS OR K E Y WORDS

Environmental Monitoring

Environmental Compliance

1 1 . REFERENCES OP RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

1. Kennedy, W.E., Jr. and М.Л. Mueller. 1982. Summary of the Environmental Dose Models

Used at DOE Nuclear Sites in 1979. PNL-3916, Pacific NK Lab, Richlnnd ИЛ

2. US Dep.of Energy 1982. Summary of Annual Environ. Reports for CY1980, DOE Nuclear

Sites. DOE/EP-00J8, US DOE, Washington DC

V.ANALYSIS AND EVALUATION OF RADIATION HAZARDS RESULTING

FROM THE OPERATION OF NUCLEAR FACILITIES

135

ARGENTINA IAEA/HPRA/IMo.11 ISRAEL IAEA/HPRA/No.11

METODOLOGIA РЛРА LA DFTERMINÍCION DEI. RIESGO RADIOLCGICO

DERIVADO DEL TRANSPORTE POR CARRETERA DE ÁGUA TPITIADA

EV£.luaci6n d eriosqos

3. AUTORES O iNVESTiCAOOntS

Reyes, Rubén; Menossi, Carlos; Segado, Roberto; Palácios, Elias

Se présenta un modelo probabilîstico para evaluar ei riesgo radiolóqico derivadodel transporte por carreteras de agua tritiada en tambores de 200 Its. Se parte de un mo_delo de clasificaci6n de accidentes según su qrado de severidad con una tasa de ocurren_cia asociada, a partir de la cual se évalua la probabilidad individual de que una perso-na (transeunte o habitante) ínvolucrada en el accidente, incurra efectos inducidos porla radiaciÔn.

Para cada grado de severidad Io cual implica un porcentaje dei volumen total dei Иquído derramado, у el volumen transportado, se infieren Ias características dei derrameA partir de estas características, de Ias condiciones meteorológicas médias imperantesen la zona bajo anâlisis y la concentraciõn de actividad en el líquido transportado, seévalua la dosis equivalente efectiva en que incurriría ei indivíduo mâs expuesto a Iasconsecuencias dei evento accidental.

Dicho valor de dosis estará asociado con una cierta probabilidad, Ia que es funciõnde Ia probabilidad de que xnperen determinadas condiciones meteorológicas; ocurrenciafraccional de un cierto grado de severidad dei accidente y ocurrencia fraccional de crueun cierto grado de severidad ocurra en una zona de densidad poblacional establecida. Co-mo resultado dei anâlisis esbozado y asociado con un valor de probabilidad de ocurrenciadei accidente se obtienen conjuntos de valores que relacionan volumen total cV líquidotransportado con la concentraciôn de actividad de tritio en el água y con le. aosis equi-valente efectiva en el indivíduo más expuesto.

Canisión Nacional de Energia AtômicaGerencia de Protección Radiolôgica y SeçruridadAvenida dei Libertador 8250(1429) Buenos Aires - ARGENTINA

IRGANiZACiON U ORGANIZACIONE5

1983, 1984.

PROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O N0 LIMITADA-INFORME PRESENTADO PARA PUBLICACION

6. DESCRIPTOnes O PALABRAS CLAVE

- Road Transport

- Heavy '."ater

- Radiation Hazards

- Dose equivalents

- International contamina-

•i-_s AMO ! ' . ! • - - ; .*

Environmental Protect ion as a Factor in Reduc ing the lïad ío-loyical Fffetts duc- to an Accident in a Nuclear f'uwur Plant

AnalvHÍs л\\Л 1 J LEvaluation ol ! 'Radiation Hazards andP r o t e c t i v e Actions (V)

Tadmor, Jacob and Koch, Jean

effects in an unprotected population. Л research project was initiated to invest igafthe alleviation of radiological effects by different protective actions designed

for the different irradiation mechanisms contributing to the external and internalradiation doses. They include : sheltPring, evacuation, fi ltration etc. The behaviorof populations during emergenices will also bf investigated, to evaluate theacceptability oî different planned emergency actions, as means of reduction ofradiation doses and consequently of radiological effects.

Soreq Nuclear Research CenterVavne, 70600 ISRAEL

F/tOM: 4 /ДЗ

«WOfflPETX- RESEARCH W PROGRESS -

s

Radiation AccidentsAssessement of Doses and

effectsEmergency ActionsRadiation Protection

I

ы00

POLAND IAEA/HPRA/No.11

A COMPUTER CODE C0NSID3RING TH3 ANALYSIS OFBAMOACTIVB CONTAMINATIONS FROM THE CCOLIHGSYSTEM OF THE WWEK REACTOR

Analysis andEvaluation ofRadiation Hazards

Zdzislawa Grosicka

4. ДН1КАСТ

A mathematical model is presented for calculating:

- corrosion and fission products activity;

- the activity of the tritium and oxygen activity

in the reactor cooling system. The results of these compuàftions are

activities deposited on the core walls, on the steam generator and

pipeline walls as well as the activity accumulated on the filter -

as a function of the reactor operation time. The calculation of

the activity is executed with згей '.V0DA1 computer code based on the

above mentioned model. The computation was executed for the W.Ï3R-440

reactor. If necessary the ÍP0DA1 code may be applied for a reactor

loop calculation as it has been fone for NPW-ffiVA loop, for example.

Central Laboratory for RadiologicalProtection,

03-194 'Sarszawa, Poland

State Agency for Atonic Energy, Poland

FHOMtî. / 7 8TC: XI . , . 83

- RESEARCH I N PROGRESS -

Radioactive contami-nation;Corrosion pr-ductsactivity;Tritium;Oxygen activity;Computer code»

Z.Grosicka, FC.Íbrno-.viecki: "Ргоггэя oMiczen ; ояу akí-7W-osci wo3yя otiegu pierwotnym elektrowni .iadrrvve.j". PTJ, 9, s.975-932 /1979/.

THAILAND IAEA/HPRA/No.11

E AND SUBTITLE

Radon and tboron concentration at a Uraniura-thoriu.extraction pilot plant in Thailand

CHITTAPORN » P,

An e x t r a c t i o n p i l o t p lant p r o c e s s i n g raonazite sand for uranium andthorium hae boon i n v e s t i g a t e d . Monazitc sand conta ins an average of 0th%uranium -and 6% thorium» The c o n c e n t r a t i o n of radon i n the p lant atmoephero i scontinuously measured* Radon and thoron daughter products are occas ional lymeasured* Foloniup-210 i n p l a n t p e r s o n n e l ' s u r ine are analyzed. Occupationalr i s k from r o u t i n e atmospheric r e l e a s e of radionuclidoB from uranium-thoriume x t r a c t i o n w i l l be eva luated .

D MAILING ADOR

Health Physics DivisionOfEicc ot Atomic Energy for PeaceThanun Vibhavadi-R.ingsitRangkhen, Bangkok 10900, Thailand

F R 0 M 10 1980то 09 198**

-iicararcn in progress -Parti il report10 STATE С= ADVANCEMENT With Itllimltcd

PROJECT RESEARCH IN PROGRESS- d i s t r i b u t i o n .PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - REPORTSUBMITTED FOR PUBLICATION

Uranium-thorium extractionMonazitc sandRadonThoronDaughter productsPolonium-210Occupational risk

VI.RADIATION ACCIDENTS

139

ARGENTINA IAEA/HPRA/No.11 FRANCE IAEA/HPRA/No.11

Planes de emergência para centrales nucleares Protección ka-di ológica delpúblico.

Ж

Bruno, II.A.; Kunst, J . J . ; Boutet, L.

Se estudian las medidas de protecciõn del público en el caso de accidentes en reacto_res nucleares. Se analizan accidntes de baja probabilidad de ocurrenciay grandesconsecuencias radiolõgicas como son aquellos que impliquen fusion del núcleo con pér_dida de la integridad de la contenciôn.

Se han desarrollado códigos de cálculo que permiten calcu lar las consecuencias radic^lógicas de un accidente nuclear con envision ai médio ambiente, en condiciones de campo, por médio de un sistema programable p o r t á t i l . La magnitud de las consecuenciasradiológicas estudiadas, permite determinar la extension y caracter íst icas de las nie_didas de protección y por Io tanto, los alcances de los olanes de emergência necesa-rios para hacer frente a este t ipo de situaciones.

Se estudian los factures de protección de las estructuras habitacionales para prote-ger a l público de la i r radiac iõn externa o la contaminación interna por el pasaje dela nube radiact iva y los sistemas de monitorajes necesarios para evaluar las conse-cuencias y la adecuada implementaciõn de las mismas.

CNEA-CAE - Sección Intervención EmergênciasCasil la de Correo 40 - 1802 Aeropuerto Ezeiza - Argentina

7 OHGUNIZAC'ON U OHGANI/AC10NES ASOClAC

8, ORGANiZAC'OS U ORGANI/ACIONES P

IACION DEL PROGRAMA

112

19831984

10 SlTuдclO^И Ш Н - INVESTIGACION EN CURSO -хишшкмшяшкишхт

Emergency ProvisionsReactor accidentsPlanning, Management.

Bruno, H.A.; Kunst, J . J . ; Palácios,E.; Pardo, I).Análisis de la necesidad de evacuaciõn en un accidente nuclear con grandes consecuen-cias radiológicas. Implicâncias en la evaluación del emplazamiento de una central de potencia. IAEA- Seminário sobre aspectos de seguridad en relaciôn con el emplazamiento decentrales nucleares. VIENNA, 1982.

ACCIDENTS RADIOLOGIQUES

ASPECTS MÉDICAUXAi Í idfiit s tins .i

VI

H. Jammet, J.C. Nénot, N. Parmentier, A. Flury-Hérar i

4. ntSuuE

L'expérience française en matière d'accidents radiologiques ayant entraîné desconséquences sévères sur les personnes irradiées remonte à plus de 2b ans etrassemble de nombreux cas, tant d'expositions globales que d'expositions localisées.

Les recherches portent essentiellement sur (1) les moyens à mettre en oeuvre pourle meilleur diagnostic possible (dosimêtrie physique, indicateurs cliniques et biolo-giques de l ' i rradiat ion), (2) les bases sur lesquelles le pronostic peut être étayé,(3) les moyens thérapeutiques.

De plus, la nécessité de disposer en permanence d'équipes prêtes à faire face à dessituations d'urgence implique Ja mise en place de moyens opérationels et techniquesspécifiques.

S. NOM Cl *D«ICÎÎl fO:iAl£ Dt 1ЧТ*ЩК[«!НТ4Т*ИТ I«TKE"HS

I.P.S.N.Département de Protection Sani ta i reB.P. n^ 6 - 92260 Fontenay-aux-Roses

7. CTAÍLCÍtUÍNÍlíMÍJfdílíJ-.UX I1AVAW

INSTITUT CURIE - ПК

О Л - CI К

D(; _ m:K . i n d i t e l i-iTi. i

ВВОДОГ-ЯЕСНЕЬСнЕ EN COURS-R АРЯОЯТ T AÏW* g к OiX >DS5,K*ï.TARt&fpUÈ*gM>b3MKTS3xei3x l lXÏ Î&

:ï1££ -

6. Dtscmr'tu-souuDTi

- Kndiop.]U.olo-U'

- Dosimt'trtr

- It'ér.ipeiti iqut Ло

1 tis inns

- Di.t^no^í ir dot. r

].Ч i on s

i. r.itiio-

Klin-

11. rtWiEMClS Oíí^lllC^iONSHtCJNUSCUUIO^roiot ° ' N U E M | U t D Q U " H |

1)

21

31

FRANCE IAEA/HDRA/No.11

1. Т1ТЖ1 ST lOOS-TITUÍ I '

UTILISATION DE VETEMENT EN COTON POUR UNE,1

DOSIHETRIE EN CAS D'ACCIDENT j UOSIMCTRIC

J. UAKÍHE » M. РГTEL.

Le coton eût fréquemment employ » • dans l'hobillnment et unparticulier dans les blouses de laboratoire. Le principe îlemesure utilisú fait appel ù 1'Omission électronique stimulée tivfaçon simultanée h la fois optiquement (excitation UV) et the rm j-q и e m e n t (chauffage! et donne lieu aux courbes appelles opto-

t he г mo g ranimes (OTG). L 'епзешЫе de lecture ut i 1 i su, se compose

d'une source lumineuse (lampe a halo (j on e ) , d'un compteur mono-

pointe o circulíition de méthane, d'un ргоцгашшн teu г de chauffage

et un ensemble de comptage. Le systî-me est piloté рог un rainior-dinsteur. L ' OTC du coton présente un pic relativement t'* tendu auxenv i г on a de 24 5"C. L'intensiti" et la surface du pic sont corri

1-

Ы e s avec la d ci se selon une loi complexe dont la premi <%re partie

entre 0 et 5 Gy suit sensiblement une loi logarithmique:

S = So LOG( D / Do ) où Do^^O.072 Gy

Les pentes So varient considírablnment avec la nature durayonnement incident. D'aprù's les premiers résultats la p ri'dosese situe environ de 0.1 Gy.

Le signal pró sente un "Fading" au cours du tnmps comportantdeux décroissances exponentielles, la plus courte avec une tlun'-ede vie de 21 heures et la plus Ionnuс un mois.

C.E.A. CEN/FAR

DPT/SIDH U.P. n° 6

9226Ü fuNTENAY-AUX-ROSES

—iDaSIIIl'IliES

LahorntGire Physique Expérimentale

Un ivers i tú de M i ce

t я zt ii«iAn:i«t

СЕЛ / EURATOM

-ACCIDLN1S PUS

'AUX RAYONNEMENTS

1982

l e c t r u n * tetitîûiï'i'oh F r o m c ' o t C u h f i b r e s . ' -T.HARTHE '• t a l l u t -Ci. . 5 . t . r . a s u a u c q F.R.ANCC . M a r c h 1 9 H Î .G of cotton in accident rins i met гу . J . [3 Л R T H Г i;t ni I rit .ГппГ .

" h'n" 'Sôl'i'J 'St'a't'e Dos imefry ' Ottawa -CAN АО A September 1983.

f .


Tel hnic i 1 \чч i stance ro t ht1 U.S . Nue ) ear K«'Rutdt orf.ommi ss ion m Implement i пц tmergenc v f repar peines sKi't|ui ri'mpnt s

2. BROAD HEADING

Prepar cttiu-

ABSTRACT

F o l l o w i n g t h e 1Ч7Ч a c n e l e n t .IL T h r e e M i l e I s l a n d , t h e U . S . N u c l o a r B c p u l a t u r v l u m m i s b i '(NRC) b e g a n a p r o g r a m t o i m p r o v e e m e r g e n c y p r e p a r e d n e s s a t U.S. powfr r e a d o r s . TheÍ o u r p h a s e s of t h e p r o g r a m - 1) r e v i e w i n g r e a c t o r o p e r a t o r ' ч e m o r g e n c v p l a n s ; 2)a p p r a i s i ng e m r r g i ' n c у p r o c e d u r t s • oqu i pment . f a c i l i t i e s , a n d p e r s o n n e l C i i p 3 b i l i t i c < ; ; 3 )

p l a n s ; a n d U) d o i n g f o l l o w - u p i n s p e c t i o n s Lo a s s u r e m a i n t e n a n c e o t e m e r g e m . v p r e p a r e d -n e s s - w e r e c o n d u c t e d b> SRC w i t h t e c h n i c a l a s s i s t a n c e from P a c i f i c N o r t h w e s t .L a b o r a t o r v t o d s c c r t a i n w h i T h o r r e a c t o r o p e r a t o r s w e r e c o m p l \ m o w i t h NRC r e g u l a t i o n sand t a k i n g a c t i o n s t o p r o t e c t nuc 1 e a r m a t e r i a i s , t h e e n v n u - - - n t , and t h e publ к .

The f i r s t two p h a s e s o t t h e p r o g r a m r e v e a l e d some m a j o r w e a k n e s s e s : n e m e r g e n c vp r e p a r e d n e s s . The f i v e a r e a s most common i y n e e d i n g i m p r o v e m e n t wrre on*, i t e e m e r g e n c yo r g a n L ? . a t i o n , eme r gene v c l a s s i i i t a t i o n svs t .em, n o t i f i c a t i o n p r o c e d u r e s , ace i d e n ta s b e s c - n e n t , and r a d i a t i n n e x p o s u r e c o n t r o l . These w e a k n c b s c s and s u g g e s t i o n s f o rp r o g r a m i m p r o v e m e n t w e r e r e p o r t e d m w r i t i n g ( o each reaLtor operator. O b s e r v a t i o n ofa n n u a I e m e r g ^ n c y p r e p a r e d n e s s e x e r c i s e s inci f o i l nw-up i n s p e c t i o n s h a v e a l s o b e e n u s e dt o p r o m o t e p r o g r a m i m p r o v e m e n t s ,

The \RC p r o g r a m h a s r e s u l t e d in s i g n i i i c . int and c o n t i n u i n g improvement s i n e m e r g e n t yp r e p a r e d n e s s a t I!. S. p o w e r l e a c t o r s a n d i n g r e a t e r p r o t e c t i o n of t h e h e a l t h лп<\ s a t e t vnf u t i 1 i t v employee s a n d t h e p u b l i t .

LING ADDRESS OF ORGANIZATION OOING T

BdlI el le-NorthwestP.O.Box ЧЧЧR u h l a n d , W.\ 4^352

Emergent v Preparednesrgenev Exercises

Power ReactorsEmergency Plansbmergent v Procédures

ASSOCIATED QPGAN'ZATIO^ISl

1J.S. Nuclear Rfgu la tory Commi s s

SPONSORING ORGANIZAT1ONIS»

U . S . Nuc l e a r R e c u U t o r


1Q STATE OF ADVANCEMENT* Й Ш б ¥ - RESEARCH IN PROGRESS -

1 . M . P . M o t * I I c r , T . l ' r b a n i k . \ . h . I V b r n s i i - r s , " C L f c A R i C a U u U t e s L o g i c a l L v a c u a t t o n a n dR e s p o n s e ) д i . e m - n t T r a n s p o r t a t i o n N e t w o r k M o d e l t o r t h e C a h u h i l i o n o t E v a c u a t i o nl i m e t s t i m a t . ' s . M M ' R h ( , / ( R - 2 ' . O i , M a r * h l ( ) t f 2 . 1 , M . I » . M o e l U r , T . l ' r b a n i k . M . A . M c L e a n .• \ . h . l i c s r o s n r s . " \ n I n d e p e n d . ' i u A s s e s s m e n t o t K v a t u a r j o n T i m e F s t i m a t e s f o r a P e a k1 4 i p t i l . i t i o n S c e n a r i o i n t h f Ь т . т ц е т и ч P l a n n i n g Z o n e o f t h e ^ " i b r o c k N u c l e a r P o w e r S t a t t _

VII.EPIDEMIOLOGY OF RADIATION DAMAGE

143


ENQUETE EPI0EMI0L0G1QUE SUR LES MINEURSD'URANIUM FRANÇAIS Epidémiologie des

rad io lés ions .

H. Tirmarctie, J . Chameaud, J . Piechowski, J . Pradel , N. Parme'ntier

«. nCSUMt

Une enquête épidémioîogique sur les mineurs d'uranium a été entreprise en France dans lecadre d'une collaboration CEA-COGEMA. Elle vise a étudier les causes de mortalité par cancer, notamment la mortalité par cancer bronchique,et d'établir une éventuelle relationentre l'exposition au radon et à ses descendants et l'augmentation du risque de cancer.A. Protocole de l'étude

Tous les agents ayant le statut mineur seront recensés dans cette enquête. L'étudeportera essentiellement sur les mineurs présents pendant les quinze premières annéessuivant l'ouverture des mines et qui risquent donc d'avoir été exposés à des dosess ign i f i ca t i ves de radon dans le passé.Pour les premières années suivant l'ouverture des mines, la dosimétrie ne peut êtreestimée qu'à partir de la connaissance du siège minier et du type de travail exercédans cette mine. A partir de 1956, i l existe une dosimëtrie d'ambiance fiable permet-tant d'attribuer une exposition relativement précise à chaque mineur.Une fiche clinique a été établie afin de tenir compte des co-facteurs de risque tels letabagisme et l'alcoolisme. Elle sera remplie par l'équipe des médecins du travail 'desmines.Les causes de décès pour le personnel en activité au moment du décès sont connues. Parcontre pour le personnel retraité, la recherche des causes de décès reste un problèmenon résolu 5 l'heure actuelle.

B. Point actuel de l'enquête. La total i té de la population des mineurs est actuel lenientrecensée. Elle est de l'ordre de 6000 agents ayant eu le statut mineur avant le 1.1.81.La recherche des décédés et de la cause de décès est actuellement en cours.

b; « m u м и н и .O:IAH Dt Lmi44iM;«T»r»»r i m . n . » b. òtsc*ir*twu OUT/OTS cLrJ ' '


COMPAGNIE GENERALE DES MATIERES NUCLEAIRES (COGEMA)

CE.A.COGEMA

ot, ... 1981

* •— indéterminée

- Mineurs d'uranium- Radon- Cancer du poumon- Epidëmiologie- Risques radiologiques

The French epidemiological study on uranium miners : di f f icult ies and progresses.К. Tirmarche, J. Chameaud, J. Piechowski, J. PradelIRPA - Radiation - Risk - Protection. 6th International Congress of IRPA, BERLIN,May 7-12, 1984.


selon le cas

1 TITLE AND SUBTITLE 2 BROAD HEAD.*,

VI]

4 ABSTRACT

T h e f n i i h i - . o r i h w . m i . . . - к . г . п ,~r\ r c u - t h •, - . , - l . . | , i . i , i m | i n l , , | , „ , , „ , ,. J ,, , , , T | , , , , , r . , ,

i n i i ' i ; r . l ! i - ( l i i H i i p i t . ü H i l К л 1 ! 1 -il i o n t \ j K i 4 i r * 1 - i t i > r ; n , i t i 11:1 ^ \ s i . ir. i ^ P i 1 t o M L n f м 11 1 , 4 d

I . r U . U c i i l .11 r i v , ™ ? I , 4 Ï O . . ' C l . l X X i i n i 4 i . i l . - f . i t . > r i 1 1 1 J t o r n p . . , , , , . . u , , r k . r - 1 1 . , ,

4 ' , , ' H H ' M 1 . U I 1 V , I n r m o r H c n i m o И ф Ь п м ч . I n , i , ! i i l i o n . t h , ( o m | , u l . . r ^ v 4 1 . -, . i l ! , . „ • .

с И ' ч м в д . n u l r o l r i f v . i l 0 1 r II 1 0 0 n u l l i e n d o c u m i - n t s t r n T i m i c r o l i l m . i l.u-, м ^ n i I 1 . , 1 1 1 '

n u s t o r a n o n o o d s „ n d O - . C s . Г Ъ . > Г . s . l , , . p . i r t m . - i i ; n i | n n f i . o n t r û . т o r - , 11 l l i t i t . r . l

i k o d b \ i i i p l a v L o r 1 r . 1 n . 1 l 1 t o t h . . . I K 1 J . 1 1 . 1 l i . i s o M I U . h 1 4 I n a d . - d o n .1 l o n t r . i l l vI o r . i

I m m t h,> d,i

d s s i n i i f d p a

d a L . i s p e c i f

b 1 0 a s s a \ r o

u i h . - i r . i d i . i

Л ma i n t r.imt- \'\ ÍYM I H H Í ' '*4 < o m p n r t> r .

•mat i n n f o r sfn-( i f i t i n l i \ и1ил

•vjotd p r o v i d e d t)\ t h e

с : о t i n ( o n t r.t< t o r . I

и I L s , r a d i a i i o n [ r . n n i g . г .-чр

feenrje.

, 0 1 I к 1 l u u . s 11

O i l t . n r i l i M l s . |>,

1 4 ! I t l t u r . tit 1 r i f V .

d | i , t4 i- 1 m. 1 u O i ' s p

•.it o r l i l t : n ^ s , я к

il In . d i a

ü n d i s a d a p f . H i l f t o i , i t : l i i , . - s i n wli 11 h r n d i , i l m n w r k i s d o n

v bv 1 n s l -tut \ \ r . I 1 u- \ .4 d

\ n t \ i s ' i k i i i i t a n u d b \

l i s ] i n n u - d l ' i t t f i s , .

14 t i l l - I M I ' f l 1 . • ' .« , nf

Nnrt tuvrst 1 abor.itoru-S

Ricliland

7 ASSOCIATED DRGANIZATIONiS

UOt-R!.

9 DURATION OF

PROGRAMME

FROM Ji>/ HO

TO J / Д ]

x ижэеиохн л мжаояк ESS a-PARTIAL OR FINAL REPORT WITH LIMiTEDOR UNLIMITED DISTRIBUTION -- REPORT

6 DESCRIPTORS OR KEY WORDS

H.inlwar.

s o t t w . i n

i i ü t . i ( umtmiin t и u r n s

l iai .i К is,- M.inam-mi-nt

! Í . T r i r v . i l

l " ( . i l \ r . - i W i w r k i m -

VIII.OPTIMIZATION OF RADIATION PROTECTION

147

ARGENTINA IAEA/HPRA/No.11 FRANCE ïÂZA/HPRA/No.ii

METODOLOGIA PARA LA OPTIMIZACION DE BLINDAT :S PARA FÜENTESNO PUNTOALES

2 ТЕМА GENERAL

Optûnizaciôn dela ProtecciõnRadiol6gica


íteyes, Rubên; Barroetavena, Alberto

Se présenta una metodologia para determinar ti forma simple el espesor de blindajesde acuerdo ai sistema de limitacion de dosis recom&.-4iada por el ICRP.

El método utilizado es ei denaninado "de Ia seccHn áurea" que trás sucesivas eli-minaciones de regiones llega ai valor 6ptimo del espesox del blindage.

Los cálculos de optimizaciôn deben realizarse en base a valores reaies. En tal sent:do, se analizan cada una de las variables que interviene en 1оь "Slculos para Ia deter-minaciõn de los valores óptiiros. La utilizaciõn de esta metodologia r*=rmite hacer ei anS_lisis mediante calculadoras de mesa programables o manualmente.

Comisiôn Nacional de Energia AtômicaGerencia de Protección RadiolÔgica y SeguridadAvenida dei Libertador 8250(1429) Buenos Aires - ARGENTINA

8. DRGANIZACION U ORGANlZACIONES PATROCINADORAS

OE . /.19ЙЗ.д ... . / 1Э84,

10.PROYECTO - INVESTIGACION EN CURSO -INFORME PARCIAL O FINAL CONDISTRIBUCION LIMITADA O N0 LIMITADA -INFORME PRESENTADO PARA PUBLICACION

6. i

- Optimization

- Shielding

- Radiation Sources

"Pri it' en compte des .ispfct s ps у с ho-pe Ы ion tie la sécurité nut-liai re"

Opt imi sat i on de |la r;idi oprotect ion.

Eric Stemmelen, -leun-Pierr'1 Pages, Jean Brenot

On se propose de mieux sa i s i r les dimensions psychologiques et sociologiquesqui ы .is-tendent la perception du risque nucléaire , à la fois chez le t ravai l leuret d ns le public . La gestion de 1л sécur i té dans le domaine nucléaire doit tenircol i te de la différence entre risque perçu et risque objectif (cf.1) , de l'ensembled 's perceptions vis-à-vis des divers risques (èf.2) et des mécanismes sociaux à l ' o r i -gine de 1'acceptation ou au rejet des programmes nucléaires (c f .3 ) .

Département de Protection SanitaireLaboratoire de Sta t is t iques et. d'Etudes Economiques etSocialesC E . A . - B.P. n" 6 92260 Fontenav-aux-Roses (France)

COMMISSARIAT A L'ENERGIE ATOMIQUE

ЯГШМХ- RtCHSRCHE EN COURS -ВПЕООНСТ: ЮКЙФЯКШ хвктаянзт

Perception des risquesDétrimentGestion des risquesOpt imisatíon

1) C»1lloque.E1iabi.Lit.é..e,t.>liiintecabnUéA9.8Z,. JPuJouse, p. 31-35

"îelon l e cms

1ЛО


"Optimization of short-lived radon daughtersunderground uranium mine". ization inOpti

radiât ion protect ion .

Jacques Lombard, André Oudiz, Pierre Zettwoog

The study is a contribution to the optimization of radiological protectionin a uranium mine.

A modélisation of the alpha contamination associated with short-lived radondaughters has been carried out in a simplified underground mine. This mine is composedof a"gallery communicating with an old stope and ten active stopes. The modelling a l -lows the calculation of the effective collective dose equivalent (for seventeen miners;according to the parameters describing the role of various protection strategies. Thesestrategics combine "classical" options such as primary and secondary ventilation aswell as new ones such as electrostat ic precipitators aimed at reducing the alphacontamination of the active stopes.

The comparison of various protection strategies is carried out with a costeffectiveness analysis in view of determining the "optimal" protection strategy. Costis expressed in terms of total cost (investment + operating and maintenance cost rela-ted to ten years activity of the mine).

The study points out th«> interest of the optimization procedure as a deci-sion aiding tool within the framework of radiological protection.

Centro d'Etude sur l'Evaluation de la Protection dans leDomaine NucléaireB.P. n° 48, 92260 Fonterjay-aux-RoseS (France)

I.P.S.N. Commissariat à l'Energie Atomique

BP 6 92260 Fontenay-aux- Roses FRANCE

6. ÎÛU"Cf 111 DC flMAUCIUCMT

ASSOCIATION EURATOM/CEA-DPr

Font enay-aux-Roses (France)

9. ou*

01:— 1.82* •— 12.82

COMPLETEЯдаг R E

OptimizationUranium MiningAlpha contaminationCost-effectivenessCost of protectionRadon daughters

Contribution à l'optimisation de la protection radiologique du personne] dans me minelldVl ran turn* -Rapport -ОБЛ.- *1-984- — *K* Lombard; -A.- *Gudi:z, P. 7-ettwoog

^ÎOptimtzatîTon *o5-short-I-K-vd* rndon-daughters'ехроэиге in an underground uranium mine.ч^Сарег presented in Luxembourg, Second European Scientific Seminar Held in november 198:

Bt'h* ' an' 9tV '.*-* A'.* Oudiz', * JI 'f.õrôfiãfd,' *?.' 'Zettvtrtrg-.- *selon le cas


Bremsstrahlung field of electrostatic acceleratorsand optimization of radiation shite 1 Is .

2. BROAD HEADING

3. AUTHORS OR INVESTIGATORS Felszerfalvi, A.Z. Kiss, E. r oltay, Gy. Szabó

4. ABSTRACT In the case cf high voltage accelerators it e intensity and theenergy distribut ion cf the Lremsst r.ahlung emitted by tne accole rat iontube is closely related to the construction of the tube. From the peintof view of the optimization of the radiation shields to be built up it isof high interest to as'-re the radi at ion fie Id as the function of tubeconstruct ion and work ir.g condition of the accelerater. The same datarepresent an imprrtar т tool for tube diagnostic. Гг tensity distributions,maximum ard mean x-ray erergies were measured arourd a bMV Van de Graaffaccelerator by the "\elp of NaJ(Tl) scintillation detectcrs and Ca20i,: Tmttiei mo luminescent des iir.etc г s . Tlie application of inclines tube geometryis highly recommence*:.

5 NAME AND MAILING ADDRESS Of ORGANIZATION DOING THE WORK

I n s t i t u t e of Nuclear ?esearch, Hungarian Аса 1of Sciences. ?.0.Б. LI.H-uûQl, Debrecen, :=_:rtgary


FROM: 6 / 1 9 8 1TO 1.?/1.983

Ж О Д Х Х М F I N A L R E P O R T W I T H О Ш З Д%№ U N L I M I T E D D I S T R I B U T I O N - ) Ю

6. OESCRlPTOnSOn КЕУ WORDS

Padiation protectionbremsstrahlungTher-mc luminescent

dosemetersVan de Graaff

accelerators

A.Z. Kiss, E. Koltay, Gy. Szabó, J . Felszerfa lv i : Optical behaviour ofAcceleration Tubes Studied in Bremsstrahlung Measurements. Nucl. Inst-r.Meth. 212 (1983) 81-89

IX.MISCELLANEOUS

151

AUSTRALIA IAEA/HPRA/No.11 BELGIUM IAEA/HPRA/No.11

it

w

1. TtTLJ AND tUITITLI

Radiation Dosimetry Physics. Measurement ofelectrons ejected from molecules by protons

2. •лолрислпиа

Miscellaneous IX

1 AUTHORS OU INVUTIOATO**

D.K. Gibson

An understanding of the effects of radiation on biological materialdepends on knowing the distribution of electrons ejected from moleculesby ion impact. An atomic collision analyser has been developed to

iure the energy and angular distribution of electrons produced by

I *MO MAIUNO ЛОРМШ OF CMOAWlZATlQh ЗЛиь, ТИ4 wOMIC

A.A.E.C. Lucas Heights Research L a b o r a t o r i e s ,P r i v a t e Mail Bag, SUTHERLAND, 2232.

7. AUOOATIO о

AUSTRALIAN ATOMIC ENERGY COMMISSION.

Л. STATI ОГ ADVANC1MINTPROJECT - RESEARCH IN PROGRESS

6. DESCRIPTOR! OH KIT WOUDS

Radiation dosimetry.atomic collisions-angular distribution,Electron analyser,

A bi-gaussian code with alternative dispersion schemes, as well as a puff trajectorymodel are verified by means of (ground-level) tracer releases (SFg) up to 10 km down-wind distance in the vicinity of Che SCK/CEN, Mol. AC the same time an evaluation ismade of the eventual benefits of an on-line implementation of these models within theframework of a computer aided emergency response system. (Emergency Plan and EmergencySurvey).

Evaluation of the possibilities of on-line modelling withinthe framework of Computer Aided Emergency Response Systems(CAERS).

J.G. Kretzschmar, G. Fieuw, P. Govaerts, I. Mertens, G. De Baere & B. Vanderborght

LES TRAVAUX

SCK/CENBoeretang 200B-24OO Mol, Belgium

7 . ETAmi

N i h i l

SCK/CEN + CEC

cCHERCH; EN COURS-

Б. OESCRir*CURlOUMQTSeLU

Accidente

Environmental doses

Modelling

Emergency Plan & Survey

. Govaerts, I . Mertens (1983), Computer Aided Emergency Response - R•' *âf the" SCK/CÈfli'Moli" Belgium' presented 'âtENEA Seminar on "Emergei-..paredneBB-t.Real-Tiee-Diffusion-Models" •Roma, 27-28.06.1983

R and D workincy Pre-

* selon le cas


New Medical Diagnostic X-Ray Protection Survey Programde Janeiro-Brazil. Miscellaneous

Motta, H.C; Araújo, A.M.С.

4. RESUME N

Since 1978, the State legislation in Rio de Janeiro requests,for each medical instai,

lation using ionizing radiation, protection survey performed by IRD. The diagnostic X-ray

inspection program is now under reorganization in order to Follow the new ICRP гессжшюпНа

tions and in order to be easier and more effective.

The program intended to provide a fast and efficient survey, consists in identifying

items that are not in compliance with applicable recornnendations for radiation safety,

according ICKP. This program is intended to be a model that can be adopted by all the Sta

te Public Health Departments and adds a surveillance in the diagnostic X-ray factories.

Radiation protection operation licence can give inmediately after the inspection, or

in «one special crses, by a formal declaration from the applicant informing the fulfillment

of the I'equirereni,. Futhermore, many specific and general recommendations are given in order

to L-nprove the actual status of the use of X-ray for diagnostic pur.wses.

Instituto de Radioproteçao e Dosir^ítria

Av. das Anericas !ím 11,5 - Rio de Janeiro - Brasil

СЕР: 226О2 CP: 37025

10 , 1082.

10 SITUACIDNPROYECTO - IWESTlGAClON FW CURSO-INFORME PARCIAL 0 FINAL CONDlSTRIRUCION LIMITADA 0 WO LIMITADA-INFORME PRESENT ADO FAHA Î'UBLICACION

Protection SurveyDiaynobt ic X-RayInsect, ion


1 T ITLE AND SUBTITLE

PROTECTION AND PRESERVATION OF IRRADIATED PHOSPHOLIFIDS

RADIATION PROTECTION

C.L. Greenstock and R.P. Whitehouse

Different types of radiation damage to phoephollpids and their chealcal modifi-cation are being monitored and quantified using a newly developed HPLC system.

L-Cephalln and L-Lecithin, containing saturated or unsaturated fatty acid aidechains, have been Y-irradiated In a variety of polar solvents, and the radiation pro-ducts detected with a far UV detector (205 nm) after partitioning on a normal phase,silica gel column. Three types of radiation damage are separated by this process:fragmentation producing free fatty acids and lysolipids, radiâtion-induced or cata-lyzed peroxidation and autoxldation, and post-irradiation damage. These productshave not all been Identified, but can be resolved Into the three categories for ana-lytical purposes* Total radiation damage Is simply assayed by the lose of abeorbanceof the HPLC peaks corresponding to the starting phoaphollpid.

Alcohols, glycerol, ethylene glycol and DMSO, alone, or In aqueous mixtures, allprotect against phosphollpld radiation damage If present during Irradiation. Theyalso prevent autoxidation and post-lrradiatlon deterioration, and preserve unlrradia-ted phospholiplds against autoxidation, suggesting that free radical chain reactionsare involved in both types of damage. The efficacy of solvente to preserve or pre-vent degradation in phosphollplde is correlated with hydroxyl radical (*0H) sca-venging potential. Preliminary studies Indicate that thiols and antloxidants arealso effective protectors, Implying that 'OH reacts with phoephollplds by hydrogenabstraction and that this in be reversed by any hydrogen donor.

5.

Medical Biophysics BranchWhiteshell Nuclear Research EstablishmentAtomic Energy of Canada Limited Research CompanyPinawa, Manitoba, Canada, ROE 1L-0

FROM 1TO I

83


6. DESCRIPTORS OH KEY WORDS

Membrane radiation damage

Lipid peroxidation,Free radicals, H-donation,•OH scavenging, HPLC

Product analysis,

Radioprotection,

Preservation

GERMANY, FEDERAL REPUBLIC OF IAEA/HPRA/No.11 INDIA IAEA/HPRA/No.11


Testing and optimizing a mutation monitoring system for man.

2. BROAD HEADING

3. AUTHORS ОЙ INVESTIGATORS

Altland, K,, Hackler, R. and Rossman, V.

The research program aims at the development of â permanent control of the averagehuman mutation rate based on an electrophoretic screening for protein variants fromdried newborn blood samples provided by the phanylketonuria screening program. Fastmethods have been developed in this laboratory for the detection of genetically de-termined variants of several proteins including the alpha-/ beta-, and gamma-globins,albumin/ transferrin, apolipoprotein A I, carbonic anhydrase X, 75-beta -globulinand a yet non-identified protein from erythrocytes. These proteins are under controlof at least 10 autosomal structural loci and can be tested from a total of samplematerial equivalent to 1/13 of one of the six blood spots on a Guthrie-testcard.The result is a screening procedure for genetic variation at about 20 parental lociper sample. The short dated goal of the research program is to integrate and optimizethe developed electrophoretic procedures to solve the problems of reproducability, re-trieval of data/ necessary family studies, e tc . , and to reduce the costs to a possibleminimum of a screening unit with a capacity of 50000 sample-tests or one million locustests per year. Thereafter an attempt will be made to measure the human mutation rateas it turns out under the conditions of the optimized procedures. As far as possiblethe detected protein variants will be checked for their aminoacid exchanges to provideinformation on the 'type of detectable substitutions. From the outcome of the researchprogram a solid data base is expected allowing decisions on the application of thetest system as a permanent control of the average mutation rate in large populationsunder the conditions of rapidly changing exposures to mutagens.

Justus-Liebig-UniversityInstitute of Human GeneticsBiochemical LaboratorySchlangenzahl 14D-6300 Giessen 1, Germanu-West


8. SPONSORING OnOANIZATIONIS)

- "Federal Ministry of the InteriorFederal Republic of Germany

- commission of the European Community - Science,Researchand Development

FROM: 07/ 1983TO: W/ №86 or later*

10. STATE Of ADVANCEMENTФШтшт- RESEARCH IN PROGRESS -

6. DESCRIPTOR OR KEY WORDS

- mutation monitoring- human mutation rate- phenylketonuna- electropnoretic

screening- dried blood samples,

use of


Vogel, F. and Altland, К. (19В2): Utilization of material from PKU screeningprograms for mutaion screening. In; Bora,К.С et al.(Eds.), Progress in MutationResearch 3:143-157

Altland, K. ,Kaempfer,ti. ,Forssbohm,M. , Werner, W. , in : Bonnè-Tamir, В. (Ed.) :Human Genetics:Дзе unfolding genome. Alan R. Liss,tiew York, 1982,pp. 271'«-287

inalyaia of Неату Eleaenta by ZBT

2. BROAD HEADING

Uiotlluioui

Iyer M.R., Chakraborty P.P. and Sabaarabudhe S.G.

4. ABSTRACT

X-ray fluoreacenoe aoalyala uainc a Co-57 exciting aouroe la employed to analyaah«av7 al«tnta In Tarlova aatrioe* of aaaplaa, fb* ajatas oonaiata of а ДОЗ 0ad«t*otor and a «ioroprocaiaor Daaad 4 К Multichannel Analysar daTalopad io the HealthFbyaiaa Division. Analyala of uraaiua and thoriua In povdar aaaplaa baa Ъаааatandaxdlatd. Typical uraniua oontaot in rook pboaphata aanplva ia foxmd to ba ID th«

of 50 to 80 ррв. Tba aaaaltlrlty la about Ю pjau

Oala» tha taoh&iqua a BOD dee t mot IT* aaaay «athod for aaalyala of Pn/U ratio 1лany type of KOX aaaplaa haa b—n d «та loped. Tha ratio of tha latanaitiaa of к x-rayafroa Pu and 0 aftar oorraotloa for the ralatiTa «ffioiaooy ia related to Pu/U atoaratio oaing ttoeio data on photo aba or pt ion oroai aaetion, fluoraaaaooa yield u ábraochlBéT latanaity. Th» relatif» affiolency oorraotloD ia a*de froai tha aaaauraaiaDton tha ae*ple itaalf aaklnc tha aethod independent of any atandarda. Tha method (ire*a preciaion of 2* for a 5 ainute aaaay. On line prooaaaiDg of data in tha aicro-prooeaaor to iva tha result loatantasaoualy вакав i t a potential f laid ayataa forroutine uaa*

Health Phyaloa Diriaion,Hiabha itoaio Reaearoh Centre,Boabay 400 085

7. ASSOCIATED OflGANIZATION(S)

8 SPONSORING ORGANIZATION(S)

Bbabha Ato«lo Baaaaroh Cantv»

PROGRAMME

FROM: .

TO"/1962/1963

l u 5TATE OP ADVANCEMENT

nnajccT - псосАПС ряввяеэоPARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION - ПСРОПТ

(on dwtmatlT»Х-г«у tltur««e«BO*lOZrwltnriroiM«nt«


СП INDIA IAEA/HPRA/No.11 ISRAEL IAEA/HPRA/No.11


Study of trace el*a»nt* In tobacco and eaok*oeroon aonozlda In Indian cl<antt* an! bidi

2. BROAD HEADING

MUeallJuuou*


Itlahi*, U.C. and Shaikh, G. I.

ABSTRACT SMklng and other u»a of tobacco m u l t in *xpo*u» of th* paraon tonatural radioactivity and toxic «laaanta pnaant In th* mckm. »uel*ar ttchniqu»» a nconr*ni*nt for th* aaataaaánt of toxic altaanta.

About 20 trace «laaanta pre*ent in chawing, amff, bidi (Indian cigars) amciiarette tobacco* wara «abatad ualng lnatruaant»! neutron aot i«t ion analyala andS*(U) gaana aptctromatry. To dataxaina tract alaaanta pnaant in clgantta anl bldi«шок* In total partlculatt mttar m p l n , an automatic amoking васЫпа ша dereloped,«laulatlng huaan aaoklng patttm. Trace alaaantt in elg*r*tt* and bidi aaok* war*analyaed by IMA, ualng Uninnltjr or Kentucky Btftnnw clgantt* 2B1 aa «tandaitf.Aa, Ba, Br, Od, 01, Co, Or, Ou, Bu, Ï*, Hf, Hg, I , 1л, * , яа, Ho, Sb, Зс, ТЬ, Znaxa the e lmnt* «май™!. I»T*1* of Ba, Br, Or, Ou, Я>, fc, Вь, Zn n n found inth* rang* 176-295, 102-211, 3-18, 41-106, 597-4017, 113-151, 8-44, 12-118 рря andof Co, Od, la, Sb, Sc, Thw*n 400-820, 102-516, 600-1120, 60-100, 70-658, 140-1253ppb, r*ap«etÍT*l7*

I»T«1» of carbon monoxld*, ona of the toxic gae, pnaant in cigarette andbldl saok* w»r* alao »tudl«d, I«T*1* wen in th* range of 15000 to 42000 ppm inTarlou* brand* of clgantt* and bldi авока.

5. NAME AND WAILING ADDRESS OF ORGANIZATION OOING THE WORK

Dr. О. С KlahraBead, Air Monitoring SectionBhabba Atomic Baaaareh C*ntnTroBbajr, Bombay i 400 085


Ill

8. SPONSORING ORGANIZATION(S)

Bnabba Atcadc Bensrch Cantr*ВожЬ«7 ! 400 085I n d i a


FROM: . . / . . 1 9 7 9TO: . . / . 1 9 8 4

l u STATE OF ADVANCEMENTPROJECT - RESEARCH IN PROGRESS -РЛРТ1Л| ПП Г1МЛ1 ПГТППТУУ1ТН I 1М1ТГРОП UNLIMITED DICTniBUTION RinOBTOUDMITTCP ГОЯ PUDLICATIOW


Traça eleiente inchawing an) anuff tobaccoclgantt* and bldiraoklsg, CO 1*те1* Intobacco eok*.

. REFERENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATORY

Determination of trace el«*nt concentration of Indian clgantt*tobacco by lnatiunental neutron aetiratlon annljal».

Лепт», U.C. and Shaikh, G. I .J. НеЛ1оаа>1. Сп«в. 78 lo . 2 (1983)

1. TITLI AMD «UtTlTLi

A Comparative Probabilistic Risk Assessment of Nuclear

and Fossil Fuel Power Plants - Methodology

2. MOAD MlA

Risk

Comparison of

Power Plante (IX)

1 w i x n i s m i n u T n i Stern, Eli and Tsdmor,Jacob

A methodology for comparing the adverse health effects of nuclear and fossil fuel

power plants has been developed*. The main health effects of both types of power

plants (i.e. early and late fatalities) are calculated using probabilistic methods,

and the results are presented by complementary cumulative distribution function

curves. The health effects of both types of power plants are presented on an equal

basis. The uncertainties in the risk curves have also been analyzed. It is shown

that the width of the uncertainty bands (that is, the ratios of the expectation valuei

of the 95% to the 5% curves) may vary from sice to site, depending mainly on site-

specific population distribution patterns. A methodology for consideration of these

uncertainties in the risk comparison process has Ьегп developed. The risk comparison

and decision making process is performed by comparing risk curves to each other using

decision-making methods developed in the field of economics for portfolio selection.

The methods, which are baaed on the utility theory, permit the comparison of risk

curves even when the curves intersect each other.

S. 4 * M | AND MAILING А О О М Ш О* ОЯСД^ПХЛТ

Israel Atomic Energy Commission

P.O.Box 7061, Tel Aviv 61070, Israel

7. AiibciATio e

8. SPONSORING OflatAMlZATIONtt)

: . . / . 7 9. . / . 8 3

8. OUCtlFTOM QR CIY KWOKM

Nuclear Plants

Fossil Fuel Power Plant!

Probabilistic Risk

Comparison

Uncertainty Bands

Decision Making

1ЛJ

ITALY /AEA/HPRA/No.11

Vlntwel lular SH-ic obtaining compounds in the repair mechanismof radiation damage"

E C[hCHAl.E :

V.Capuano', M.QumtilíaniV G.Simone1,1* M.Tamba'."

One of the most important factors determining cellular resistance to radiations is thepresence of SH-containing compound, particularly of reduced glutathione (GSH). Thechemical repair of radiation damaged biomolecules is carried out, in fact, by hydrogendonation by such compounds. Our studies, involving same chemical and biological "nodelsystems such as alcohols, purified enzymes, bacteria and mamnalian cells, provide somecontribution to the understanding of the role of GSH in affecting cellular response andoxygen enhancement ratio {OER).

Complete repair by hydrogen donation from GSH is seen only with alcohols, while withcarbohydrate radicals this does not happen. Pulse raciiolysis experiments showed thatthe influence of GSH on radiation inactivation of yeast alcohol-dehydrogenase is stronglyprotective, and much more so in nitrogen, giving a large OER. In the expefiments withE.coli cells we treated them with buthionine sulphoximine in order to depress th« GSHsynthesis. Sensitization was observed both in oxic and anoxic conditions- No clearcorrelation with intracellular GSH content can be established. Irradiations of CHQ andof a mutant line UV-sensitive 43R0 cells exhibited a reduced OER in the case of themutant line. The SH content was slightly less than in the parent line, so no apparentcorrelation of radiosensitivity with SH content was observed here.Further studies зге inprogress on human fibroblasts and artificial mutants with reduced OER.

ÉNEA, Dosiînefcry and Biophysics Laboratory^ C.R.E. CasacciaP.O.B. 2400 - 00100 Roma, Italy

CNR 1st. Tecn.Biomed. via G. Morgagm 30/E Roma Italy

CNR Istituto F.R.A.E. via Castagnoli 2 Bologna Italy

8. SOUmCCfM D£ f

PC; ,.,.Jm

A : - J...

- F.f.CH£RChE EN COURS -RAPPORT PARTIEL i ï ï 2 2 3 ^ 3 ADIFFUSION Z ^ Î : Ï S £ 1 £ Ï ILLIMITEE -RAPPORT SOUf.'.'S POUR PUBLICATION

Oxygen enhancement rat io.Glutathione.

M.Quintiliani. Cellular thiols and radiation response.Baxendale Memorial Symposium.1st.Frae Bologna Italy 1983

X.RESEARCH PROGRAMMES AND PROJECTS

159

BELGIUM IAEA/HPRA/No.11

Research programme of the Radiobiology Department ofthe Nuclear Centre of Mo I, Belgium.

3. AUTEURS RU CHIRCMEURS

J.R.Haisin, Chief of the Radiobiology Department

The Radiobiology programme is composed of the following major projects :

- somatic effects t»f ionizing radiation ;- genetic effects of ionizing radiation and chemical mutagens ;- metabolism and biological effects of radionuclides in mammals ;- effects of radioactive and non-radioactive pollutants on ecosystems and associated

toxicologie studies.

As part of these major projects, special attention has been paid to : the pathogenesisof radioinduced leukemia and ostttosarcoma ; the pathogunesis of non-neoplastic lateeffects in irradiated lung and brain ; the relative biological effectiveness of50 MeV neutrons and gamma rays for leukemia and cancer induction in mice ; factorsdetermining the relative radiosensitivity of chromosomes in different mammalian species'the toxicity of radium-226 incorporated in the bones of mice ; the behaviour of tritium'in an agriculture environment ; the biological availability of americium-2A1 by a fresh-*water invertebrate ; the transfer of technetium in the animal food chain ; the radio-biological surveillance around nuclear power station sites, etc

S NOM ET AbMSbt *OÍTAL£ Dl L*E'*»^SfLKSTRAVAUBDépartement de RadiobiologieCentre d'Etude de l'Energie Nucléaire (C.E.S./S.C,t.)B-2400 MOL, Belgium

EyratomMinistry of Economic Affairs, Ministry of Public Health,National Foundation for Scientific Medical Research(FKSM), Fonds National de la Recherche Scientifique (FNKS

1997sa»©»

- R è

4 9

'SRCHE E N C O J E S -

6. I

d(50)-Be neutronsgamma irradiationfractionated exposure1ífe shorteningdisease incidencecarcinogenesistechnetium-95radium-226amcricium-241

BELGIUM IAEA/HPRA/No.11

Feasibility study for using a fluorescent laser detector forin-situ testing of HEPA-filters in nuclear ventilation systemsj P r o g r a m m t î S e t p r o j e t

de recherche

J.P. Deworm, W. Siegers

very etticient nicer or composii-e HUKI эуы-сThe effects of temperature and humidity will al

5. NOM ET *04ESEE POSTALE СLES TRAVAUX

SCK/CENBoeretang 200B-2400 Mol Belgium

7. !

Nihil

№_^_-«.Fv=CH£RCH= F.S COURS -

J OUMOTSCLU

AerosolsFilter testing

'.' .J,P,.Dewpna,.Filtecbn..Conference.London.1983,.Feasibility of the laser spectro-raetry technology for in-situ testing of HEPA-filtratLon systems in the nuclear

- ihaUst'ry".

се1зя le cas


t TTTLE ANO SUBT(T(,C

Study of Co-Carcinogens in a Uranium Mine Environment

IResearch Programmes andProjects

CHAMBERS, D.B. et al

4. ABSTRACT

There are many physical, chemical and biological agents in uranium mine/raill facilities

which may be carcinogenic themselves or co-carcinogenic with other radioacti\e or

non-radioactive substances found in such facilities. This study attempts to identify

such agents in surface and underground uranium mines and in typical mills and to

quantify the estimated exposures experienced by mine and mill workers. Recommendations]

with respect to worker protection from these hazards will be made.


Senes Consultants Ltd.499 McNicholl AvenueWillowdale, OntarioCanada M2H 2 C



Saskatchewan Mining Development CorporationAtomic Energy Control Board

FROM. * / 8 .2TO- . 3 / 8 3

PROJECT -PARTIAL OR FINAL REPORT WITH LIMITEDOR UNLIMITED DISTRIBUTION

6 . D E S C R I P T O R S O R K E Y WORDS

exposuredosimetrytoxicityuptakeminesmillsradiation protection

FINLAND IAEA/HPRA/No.11

Establishment of a nationwide technical qualityassurance program in radiotherapy

2 BROAD HEADING

Researchprograms andprojects

A. Vaanãnen and H. Jarvinen

A nationwide program for technical quality assurance in radiotherapyis being established. The scope covers regular tests for each individualtherapy machine (of 7 different types at 9 therapy centers) and thecontrol of their dosimetry procedures. The present centralizedresponsibility of the Institute of Radiation Protection for absolutedose measurements will be supplemented by increased local know-howand responsibility of the therapy centers- The therapy centers arepushed to formulate detailed programs of guality assurance tests whichenable them to maintain a continuous acquaintance of the operatingconditions and performance of each therapy machine. The applicabilityof international machine standards will be studied in co-operationwith the therapy centers, and the most appropriate and useful testsin respect of the individual features of the machines will be identified.TLD postal intercomparison procedures will be studied and developedto cover also "the standard reference treatment" option. In dosimetry,fundamental characteristics of selected commercially available dosemeterassemblies will be tested and verified in accordance with an internationalstandard (IEC Publication 731).


Institute of Radiation ProtectionP 0 Box 268SF - 00101 HELSINKI Î0 FINLAND

SPONSORING ORGANlZATI


FROM 1 , 8 3TO 1 2 0 4

PROJECT"- " RESEARCH IN PROGRESS -РАПТ!А1.-ОП riNAL ПХРОПТ WITH LIMITED

Quality assurance,Radiotherapy machinesRadiotherapy dosimetr>Standardization

JAPAN IAEA/HPRA/No.11 NETHERLANDS IAEA/HPRA/No.11

Project. .Ч'ссезгс:; on zhc Лсд- :;.zxent ofExpouurej to E:iviron.T.entr-l Rsdi-tion

Effects of ' ' M-•Radlation.

Environmental r t jc ie$

Tanak'a' G.," 'Jed /.beaxki Í--,(General Leader), f.atsuzawa ::.,Ic.:ikawa R.,. (Leader) r.nd /(J scientif ic s taf fs

; Ав1-р*ст The project includee studies on various o^ectc of transferand irradiation mechanisms of environmental r:áionucllã-зс tliroufh thepathwc.ys fro:", nuclear rlrnts to human population»1) Studies on estimation of radiation doses in relation to transfer ofradionuclides through pathway from JO 11 to agricultural products.2) Studies on estimation of radiation doreu in relation to transfer ofradionuclides in marine environment.3) Studies on estimation of radiation doser: in relation to inhalationof radionuclides and external radiation.h) Studies on ingestion of radionuclides and metabolic behavior ofradionuclides.5) Stuulan on population doses -nd Reference Japanese Kan.Emphasis is placed on radionuclider of ctiriide reries (Pu etc.),corrosion products (Co, Fe, Kn etc.) and some of fission products(Sr, Cs, Ce, í?u, I etc.) to be appeared in radioactive v.-astes fromnuclear power plants , fuel reprocessing plants and о trier relatedfacilities»

K?tional Institute of Radiological Sciences9-1,L-chôme,Anarav/a, Chiba-shi, £60, Jrnon

! Laboratory for Radioecolocy» IIAKAîir. TOi National Institute of Itediolocical Sciences| Isozal-.i 2)509,;.at:arainato-shi,Ibaralîi,311-12, Japan

! Internal Contamination, External Radiation, Cri tic1 J P' chvaysi Hunan Data

_;-Pl nts*, Soils! Aninalc' Marine "iot-?i?sion ProductsCorrocion Products

"" Plutonium

Science and Technology Agency, Japan

См h i 833 / 87

Neutron dosimetry instrumentation for radiation protectionand radiobiology - response of high-pressure lonizationchambers

determination ofdose equivalent

J. Zoetelief, L.A. Hennen and J.J. Broerse

Radiation fields outside technological and biomédical mstaUattonsgenerally consist of different types of particles such as neutrons and photons ofvarious energies. These particles have different quality factors and an assess-ment should be made of the effective dose equivalent for radiation protection pur-poses, in consequence the development of detectors having a réponse proportionalto dose equivalent for a wide range of radiation quality is required. Operation ofionization chambers under higher gas pressures will increase the sensitivity. Thesaturation characteristics as well as the pressure dependence of the reading aredependent of the quality of the radiation.

Measurements with a thimble-type high-pressure tissue equivalent (TE) ioni-zation chamber have been performed at pressures of up to 8 MPa of methanebased muscle equivalent gas for Cs gamma rays, 0.9 and 14.5 MeV neutrons.For the various measurement conditions, it is shown that radiation quality can beassessed by variation of both the collecting potential and the gas pressure.

An aluminum chamber is under construction to develop a detector with avery small neutron sensitivity. This apparatus will be used in the twin-dosimetertechnique to separate the low-LET and high-LET components of the radiationfields. The response of the lonization chambers with different gas fillings(including neon based TE, methane based TE, methane, nitrogen and argon) willbe analyzed with the aim of assessing the dose equivalent.

IMG ADDRESS OF ORGANIZATION

Radiobiological Institute TNO151 Lange Kleiweg2288 CJ RijswijkThe Netherlands

Division for Health Research TNOCommission of the European Communities

PROGRAMME

FROM 01 '8.1TO W/»1»

-. RESEARCH IN PROGRESS -

ionization chamber,high pressure,dose equivalent.

J. Zoetelief, А . С Engels, C.J. Bouts, L.A. Hennen and J.J. Broerse (19Э1).Response of tissue equivalent ionization chambers as a function of gas pressure.In: Proc. Fourth Symposium, Neutron Dosimetry. EUR 7M8. pp. 315-326.Commission of the European Communities, Luxembourg.

X SOUTH AFRICA IAEA/HPRA/No.11 SOUTH AFRICA IAEA/HPRA/No.11

MATHEMATICAL MODELLING OF NEUTRON REM COUNTERS

2 ВЙОАО HEADING

RESEARCH PROGRAMMES

AND PROJECTS


SARTORI, D E; DE BEER, G P

absorption just below 1 V i

ciency as related to the rem curve

5. NAME AND MAILING ADDRESS OP ORGANIZATION DOING THE WORK


PRIVATE БАС Х256

PRETORIA

0001 SOUTH AFRICA

ASSOCIATED ORGANIZATION15I

8. SPONSORING ORGANlZAT.ONlSl

FROM *\ ' SOTo- 1.2; 84

10.: RESEARCH IN PROGRESS -

PARTIAL С4ШНЛХ REPORT WITHHHIMIEBneXUNLIMITEO DISTRIBUTION -Я№ОЯСК

«ммютомшишешагау.


MONITORS

NEUTRON MONITORS

REM COUNTERS

MATHEMATICAL MODELS

TRANSPORT CALCULATIONS

MODERATING SPHERES

S a r t o r i , D E; De Beer, G P. A study of the Responses of Neutron Dose Equiva lentSurvey Meters w i th Computer Codes. Radiat ion P r o t e c t i o n DosimeLry v. 4 No 2(1984) p 8 5 - 9 0 .

J TITLE ANDSueTlTLE

IMPROVEMENTS ON THE PELSHIE SHIELDING PROGRAM RESEARCH PROGPJUAND PROJECTS


DE BEER, G P; SARTORI, D E; HOLLER, E U.

PELSHIE is a general-purpose shielding program using a point-kernel integration

technique. A recent investigation indicated two main sources of error in the

results. The first is the Monte Carlo integration technique when used to determine

two- and three-dimensional integrals for dose-measuring points near to or inside

very large volume sources. The second is the use of fitted parameters to a single-

medium, build-up factor function even for multi-layered shields. These two areas

are investigated in order to find improved methods to reduce the errors introduced

by the present techniques.

NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE WORK

NUCLEAR DEVELOPMENT CORPORATION OF SOUTH AFRICA (PTY) LTI

PRIVATE ВАС Х256

PRETORIA

0001 SOUTH AFRICA

FROM 8TO 12

8184

]РЕагоихЕНЕЯ1е«кPARTIAL ояшаа. REPORT WITH wwxra

OR UNLIMITED DISTRIBUTION - " "ыгаанятвшюеившапнш


SHIELDING

RADIATION SHIELDING

GAMMA-RAY SHIELDING

POINT-KERNEL INTEGRATIOhTECHNIQUE

BUILD-UP FACTORS

SOUTH AFRICA IAEA/HPRA/No.11 UNITED STATES OF AMERICA IAEA/HPRA/No.11

Os

MODELLING OF LARGE-PORE «UCLEPORE FILTERS WITH AEROSOL

PARTICLES

2. BROAD HEADING

RESEARCH PROGRAMMES

AND PROJECTS

LEUSCHNER, A H; KRUGER, J; ROSSOUVJ, JACOBA W.

Thy behaviour of aerosol particles trappod on Nuclepore filters with large pores,

is being examined experimentally and theoretically. Deposition sites are determined

as a function of operating conditions, aerosol characterist ics, previous loading

of the filter with particles and irregularities in the filter.

Aerosols are labelled with radioacLivity for macroscopic analysis and a SEM is used

for microscopic analysis.

A numerical solution of the Navier Stokes equation is used for the theoretical

modelling of deposition of particles from air flowing through a porous filter.

This project is in its final stage. The necessary documentation is being prepared.

5. NAME AND MAILING ADDRESS OF ORGANIZATION DOING THE vMORK


PRIVATE BAG X256

PRETORIA

0001 SOUTH AFRICA

ASSOCIATED OHCANiZATiQMSI

9. DURATION OF

PROGRAMME

FROM \> 79TO 12/ 83


6 DESCRIPTORS OR KEY WORDS

AEROSOLS

FILTERS

MODELLING

NUCLEPORE

.'ARTICLE DEPOSITION

Technica l Eva lua t ion of Draft ANSI Standard N13.30"Performance C r i t e r i a for Raàiobíoassay"

ROAD HEADING

Assessment ofDose to Man (Internal)

HORS он INVESTIGATORS Darrell R. FisherAlfred V. Robinson

ABSTRACT

A project titled "Technical Evaluation of draft ANSI (American National Standard

Institute) Standard N13.30 "Performance Criteria for Radiobioassay" has been

initiated. 'lhe objective of this project is to evaluate the appropriateness of the

accuracy and precision criteria specified in draft ANSI Standard N13.30 by testing

the analytical capabilities of bioassay laboratories. Two rounds of in-vitro and

in-vivo bioassay intercomparison testing are planned. The procedures far this testing

will be established according to criteria listed in draft ANSI Standard N13.30.

The program consists of two parts: a pilot study (first test run) will be

conducted among a few volunteering laboratories, and later a more comprehensive

study (second test run) will be undertaken among the same laboratories and any others

that wish to become involved.

The National Bureau of Standards will provide the radionuclides to be used in

the program. Recommendations will be formulated for any necessary revisions to

draft Standard N13.30. In addition, a manual defining procedures and methods to be

used by a testing laboratory in an ongoing certification program will be preoared.

lhe program is jointly funded by tht Jnited States Nuclear Regulatory Commission

and the United States Department of Energy.

. NAME AMD MAILING ADDRES

l îa t te l le NorthwestP.O. Box 999Kichland, WA 99352U.S.A.

F ORGANIZATION

DOE, NRC

SPÛNSOniNC ORGANIZATIONS!

DOE, NRC

FROM 10 /81TO ID/ &4


6.

In Vivo BioassayIn Vitro BioassayUrinanalysisArtificial UrineWhole Body CountingIntercomparison StudyRadiobioassay

11 REf ËHENCES OF RECENT PUBLICATIONS IN SAME FIELD ISSUED FROM THIS LABORATOR

NONE

ORDER FORM FOR REQUESTING OF SHIPMENTOF HEALTH PHYSICS RESEARCH ABSTRACTS

1. Special Notice

The resources available for the production of Health Physics Research Abstracts (HPRA) are limited. As partof an effort to ensure thjt they are used to the best effect, each recipient of this edition is requested tonotify the Division of Nudear Safety if he wishes to receive the next edition. If a positive indication is notreceived it will be assumed that HPRA is no longer required.

2. Ordering

If you wish to receive and/or contribute to the next issue of Health Physics Research Abstracts mail thisform to the following address:

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FORMULAIRE DE COMMANDE DU RECUEIL«HEALTH PHYSICS RESEARCH ABSTRACTS»

1. Note

Les ressources disponibles pour la publication du recueil «Health Physics Research Abstracts» (HPRA) sontlimitées. S'efforçant de tirer le meilleur parti de ces ressources, la Division de la sûreté nucléaire demande àchaque personne qui recevra la présente édition de lui faire savoir si elle souhaite recevoir l'édition suivante.En l'absence d'une réponse positive, la Division considérera que la personne en question ne souhaite plusrecevoir le recueil HPRA.

2. Commande

Si vous désirez vecevoir la prochaine édition du recueil HPRA ou y contribuer, veuillez remplir ce formulaireet le renvoyer à l'adresse suivante:

Health Physics Research AbstractsDivision de la sûreté nucléaireAgence internationale de l'énergie atomiqueBoîte postale 100A-J 400 VienneAutriche

Je suis intéressé(e) par le prochain recueil «Health Physics Research Abstracts» (cocher les cases correspondanteset rayer les mentions inutiles)

• Je désire être inscrit(e) sur votre liste d'adresses

• Mon adresse complète est la suivante:

Nom: (nom de famille en lettres majuscules, suivi du prénom en toutes lettres)

Titre:

Service:

Organisation:

Adresse (y compris le code postal):

• Je souhaiterais vous envoyer un (plusieurs) résumé(s) pour la prochaine édition du recueil HPRA.Veuillez me faire parvenirс une fiche • cinq fiches • plus de cinq fiches (préciser le nombre)

• Pourriez-vous adresser un exemplaire du recueil HPRA aux personnes dont les noms suivent:

Date: Signature:

БЛАНК ЗАКАЗА

НА СБОРНИК АННОТАЦИЙ ПО ИССЛЕДОВАНИЯМ, КАСАЮЩИМСЯ НАУЧНЫХ

ОСНОВ РАДИАЦИОННОЙ БЕЗОПАСНОСТИ

1. Специальное уведомление

Возможности выпуска сборника аннотаций по исследованиям, касающимся научных основ

радиационной безопасности (АИРБ), ограничены. С целью оказания помощи для наилучшего

использования сборника каждого получателя этого издания просят уведомлять Отдел ядерной

безопасности о том, желает ли он получить следующий выпуск. При отсутствии положительного

ответа будет считаться, что АИРБ более не требуется.

2. Оформление заказов

Желающие получить и/или сделать соответствующий вклад в очередной выпуск сборника

аннотаций по исследованиям, касающимся научных основ радиационной безопасности, должны

направить настоящий бланк по следующему адресу:

Health Physics Research Abstracts

Division of Nuclear Safety

International Atomic Energy Agency

P.O. Box 100

A — 1400 Vienna, Austria

Я хотел бы получить очередной бюллетень аннотаций по исследованиям, касающимся научных основ

радиационной безопасности (отметьте крестиком соответствующий квадрат и вычеркните ненужные

пункты)

• Я бы хотел, чтобы меня включили в список рассылки материалов

п Мой полный адрес:

Фамилия: (фамилия/и пишется заглавными буквами, затем следует полное имя)

Должность:

Выполняемая работа:

Организация:

Адрес (включая почтовый индекс) :

а Я бы хотел направить Вам аннотацию (и) для Вашего следующего выпуска АИРБ, пожалуйста,

направьте мне

п одну форму п пять форм п большее количество форм (укажите точное число)

о Я полагаю, что экземпляр бюллетеня АИРБ должен быть направлен следующим лицам:

Дата: Подпись:

NOTA DE PEDIDO PARA SOLICITAR EL ENVIODE "HEALTH PHYSICS RESEARCH ABSTRACTS"

1. Advertência especial

Los recursos de que se dispone para la producción de "Health Physics Research Abstracts" (HPRA) sonlimitados. Con el fin de lograr la máxima eficiência de esta publicación. rogamos a quienes reciban elpresente número que comuniquen a la Division de Seguridad Nuclear si desean recibir el próximo. De norecibirse contestacion afirmativa supondreinos que el destinatário no desea continuar recibiendo estapublicación.

2. Pedido

Si se desea recibir el próximo número de "Health Physics Research Abstracts" o enviar una comunicaciónpara su inclusion en este boletín, enviese este formulário a la dirección siguiente:

"Health Physics Research Abstracts"Division de Seguridad NuclearOrganismo Internacional de Energia AtômicaP.O. Box 100A-1400 Viena (Austria)

Sírvanse enviarme el próximo número de "Health Physics Research Abstracts" (marcar Ias casulascorrespondientes y tachar Io que no proceda)

• Deseo que se me incluya en la lista de distribución

• Mi dirección completa es Ia siguente:

Nombre y apellidos: (Apellido o apellidos con mayúsculas, seguidos dei nombre completo)

Cargo:

Servido:

Organización:

Dirección postal (incluído el distrito o código postal):

• Me interesa enviar resumen(es) para el próximo número de HPRA. ruego me envíen:• un formulário o cinco formulários • más formulários (indicar el número)

• Sugiero que envíen un ejemplar dei boletín HPRA a Ias siguientes personas:

Fecha: Firma:

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