RADIONUCLIDEANDRADIATION PROTECTIONDATA HANDBOOK 2002D.Delacroix*J.P.Guerre**P.Leblanc**C.Hickman*Commissariata`lEnergieAtomique,CEA/DAM-IledeFrance,France**Commissariata`lEnergieAtomique,CEA/Saclay,FranceISBN1870965876RADIATIONPROTECTIONDOSIMETRYVol.98No1,2002PublishedbyNuclearTechnologyPublishingRADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)All rightsreserved. Nopart of thisbookmaybereproduced, storedinaretrieval systemortransmitted in any form or by any means, electronic, electrostatic, magnetic, mechanical, photo-copying,recordingor otherwise, withoutpermission in writing from the publishers.British Library Cataloguing in Publication DataAcataloguerecordofthisbookisavailableattheBritishLibraryISBN1870965876COPYRIGHT 2002NuclearTechnologyPublishing345RadiationProtectionDosimetryVol.98,No.1,pp.56(2002)NuclearTechnologyPublishingRADIONUCLIDE AND RADIATION PROTECTION DATA HANDBOOK2nd Edition (2002)ContentsContents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5Preface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9SCOPE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9CLASSIFICATIONOFRADIONUCLIDES . . . . . . . . . . . . . . . . . . . . . . . . . . . 10PHYSICALCHARACTERISTICSOFRADIONUCLIDES. . . . . . . . . . . . . . . . . . . . . 10RADIOLOGICALCONTROL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10Externalexposurerisks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10Internalexposurerisks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10Doselimitsforworkers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11EXTERNALEXPOSURE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11Assumptions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11Distant(pointsource)externalexposure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11Exposurestoauniformlycontaminatedsurface . . . . . . . . . . . . . . . . . . . . . . . . . 12Externalcontactexposure(receptacles) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12SHIELDINGOFBETAANDGAMMAEMITTERS . . . . . . . . . . . . . . . . . . . . . . . 12CONTAMINATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12Contactexposureduetoexternalskincontamination. . . . . . . . . . . . . . . . . . . . . . . 12Decayproducts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12Decayofheavyelements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13Derivedsurfacecontaminationlimits(DSCL). . . . . . . . . . . . . . . . . . . . . . . . . . 13Determinationofremovableandxedcontaminationvalues . . . . . . . . . . . . . . . . . . . 14Contaminationcontrol . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14Detectionprobes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 146CONTENTS(continued)INTERNALEXPOSURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14Committedeffectivedoseperunitintake . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14AnnualLimitsonIntake(ALI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14Thehighestdoseorgan. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15General . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15MAXIMUMRECOMMENDEDACTIVITIES. . . . . . . . . . . . . . . . . . . . . . . . . . . 15Calculationmodels . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15Dependenceofmaximumrecommendedactivitiesonequipmentandworkingareas . . . . . . . . 15Limitations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16DESCRIPTIONOFDATASHEETS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16GLOSSARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17TABLEOFRADIONUCLIDESLISTED. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19DATASHEETS(144) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21APPENDIXHEAVYELEMENTDECAY . . . . . . . . . . . . . . . . . . . . . . . . . . . 165is abstracted or indexed in RADIATION PROTECTIONABSTRACTS, Chemical Abstracts, CURRENTCONTENTS, EnergyInformationAbstracts (Cambridge),EXCERPTAMEDICA(EMBASE), HealthandSafetyScienceAbstracts(Cambridge), INISATOMINDEX(hardcopyand CDROM),INSPEC,Nuclear Energy(CzechRepublic),QUESTandReferativmajaZhurnal.7RadiationProtectionDosimetryVol.98,No.1,p.7(2002)NuclearTechnologyPublishingPrefaceRADIONUCLIDEANDRADIATION PROTECTIONDATAHANDBOOK(2002)This handbook is an updated and expanded (2nd edition) version of the handbook with the same title publishedin1998.ThathandbookwasinturnbasedonanearlierFrenchlaboratoryguidebookAGuideonRadionuclidesandRadioprotectionbyD. Delacroix, J.P. Guerre, andP. Leblanc, publishedin1994(1). Theearlierpublicationwas very much oriented towards guidance on the handling of radionuclides used in medicine. The present handbookismuchmorebroadlybasedinitsoutlookandapplicationandincorporatesupdatedinformationtotakeaccountof the most recent ICRP and IAEA recommendations(14). The radionuclides listed in the earlier publication weresupplementedbycommonlyusedradionuclidesinthenuclear industryandinother areas. Moreover, themainpurposeofthishandbook(andits1998predecessor) istheprovisionof datasheetsandthemodelsorsourcesusedtoassemblethedata,ratherthanasaradiationprotectionguideforlaboratoryusers.This practical handbook of data for handling radioactive materials is intended for radiation protection specialistsaswellasall otherswhouseortransportradionuclides. Itspublicationshouldsatisfyamajorneed forallhealthphysics departments and is intended to assist in informing and training personnel in radiation protection. It consistsof an explanatory text followed by specic radiation data sheets for selected radionuclides. Because of the dispari-tiesintheapproachesadoptedbydifferent countries, it isessential that usersalsorefertotherelevant nationalregulationswithwhichtheymustcomply.Thepresent handbookincludes 36additional radionuclides thantheprevious edition, givingatotal of 144nuclides. Additionaldataareincludedcoveringdoseratesaboveuniformlycontaminatedsurfaces(inniteplanesource). Somecorrections todataintheprevious editionhavebeenincorporated. Thelist of nuclides is notexhaustive but those included have been selected on the basis of being most commonly used, taking into accounttherequirementsof usersinindustry, medicineandresearch. Finally, account istakenof theneedtoconsiderdecay chain productsfor several heavy elements. To thisend, an appendix is providedgiving the decay productsandtheiractivitiesasafunctionoftime(age),togetherwithdecaychartsforfourofthemorecomplexchains.Directeur Central de la SecuriteCommissariat a` lEnergie Atomique, France89RadiationProtectionDosimetryVol.98,No.1,pp.918(2002)NuclearTechnologyPublishingRADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)D.Delacroix*,J.P.Guerre**,P.Leblanc**andC.Hickman*Commissariata`lEnergieAtomique,CEA/DAM-IledeFrance,France**Commissariata`lEnergieAtomique,CEA/SACLAY,FranceAbstract This handbookis areferencesourceofradionuclideandradiationprotectioninformation. Itspurpose istoprovideusersofradionuclides inmedicine, researchandindustry with consolidatedandappropriateinformationand datatohandleandtransportradioactivesubstancessafely. Itismainlyintendedforusersinlowandintermediateactivitylaboratories. Individualdata sheets are provided for a wide range of commonly used radionuclides (144 in total). These radionuclides are classied intove different groups as a function of risk level, represented by colours red, orange, yellow, green and blue, in descending orderofrisk.INTRODUCTIONIn recent years the need for a compilation of essentialdata for commonly used radionuclides, for both practiceandtraining,hasbecomeincreasinglyapparent.Thishandbookcontainsindividual datasheetsforarange of radionuclides and is mainly intended for usersof unsealed radioactive sources in low and intermediateactivitylaboratories, industrial applications andtrans-port.Individualdatasheetscorrespondingtothedifferentradionuclides give the physical characteristics, referencetransport activities, exemption levels, contaminationderivedlimits andappropriate detectionprobes, doserates fromskin contamination, half and tenth valueshielding thicknesses, external exposure data, dose coef-cients for ingestion and inhalation, derived 20 mSvALI values, and the highest dose organ. The maximumactivities recommended to be handled on benches, underfume hoods and in glove boxes are also given. However,this information is most appropriate in laboratorieshandling lowand intermediate levels of radioactivematerials. In order to facilitate the users understanding,pictorial illustrationshavebeenemployedanddataispresentedintabularform.It shouldbenotedthat thedataprovided, althoughdrawn from appropriate recent international recommen-dations, should in no way be taken to supersede existinglocal ornationalregulations. Thedatamay, ofcourse,be used to review existing local regulations which mayhavebecomeoutofdate.The text preceding the data sheets provides the back-ground, derivation and substantiation for the data given,enabling users to satisfy any quality assurance arrange-mentsthatmaybeinplace.SCOPEThishandbookprovidesthemost uptodateinternalandexternaldosimetryinformationandcontrolcriteriaintheformofdatasheetsinaneasytouseformatfor144 of the most commonly used radionuclides in medi-cine, researchandindustry. It is designedas areadyreferencesourceof information, gatheringtogether inone place, in the form of individual data sheets, the mostuptodateisotopicandradiationprotectiondata. Theinformationincludes:half-lifeandspecicactivity,mainemissions,IAEABasicSafetyStandardsexemptionlevels,IAEAA1andA2transportvalues,externalexposuredataforarangeofgeometries,surfacecontaminationdata,detectionandlimits,shieldinginformation,ICRPdose per unit intake data by ingestion andinhalation,20 mSv ALI values and the highest organ dose, and,maximum recommended activities in Controlled andSupervisedAreas.Most of thedataprovidedarerelevant toall users.However, thesectionanddatadealingwithmaximumrecommended activities are only appropriate to low andintermediate activity laboratories. These laboratories arefrequentlylimitedtotwotothreeordersofmagnitudehigher thantheexemptionlimits bylocal or nationalregulations.CLASSIFICATIONOFRADIONUCLIDESRadionuclides have beendividedinthis handbookintoveriskgroups.TheclassicationusedisbasedontheBSSquantityexemptionlimitvalues. Exemp-tion limit values have been chosen for this purposebecause they reect both internal and external exposurerisks. Each group is associated with a colour (red,orange, yellow, greenandbluesuccessivelyrepresentdecreasinglevels of risk). Thedatasheets havebeenappropriately coloured providing the reader with a rapidvisual means of appreciatingtheriskassociatedwithD.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN10particular radionuclides. The ve risk groups have beendenedasfollows:Group1:exemptionlimit104Bq(red)Group2:exemptionlimit =105Bq(orange)Group3:exemptionlimit =106Bq(yellow)Group4:exemptionlimit =107Bq(green)Group5:exemptionlimit108Bq(blue)In the rare cases for which exemption levels have notbeendened(e.g.11C, anuclidesometimes usedformedical imaging) a group has been assigned by analogywithotherradionuclidesofthesametype.Attentionisdrawntothefact that radioactivesub-stances arealsochemical substances, thehandlingofwhichmayinvolvehazardsofnon-radiological origin.Moreover, radioactivesubstances areoftenintimatelymixed with chemical products having an aggressiveactiononthehumanbody(toxic, mutagenicandcar-cinogeniceffects). Chemical hazards shouldthereforeneverbeneglected.PHYSICALCHARACTERISTICSOFRADIONUCLIDESThe following characteristics are considered inthesesheets.Half-lives expressed in the most appropriate units(hours,days,years).SpecicactivitiesexpressedasBq.g1.ExemptionlevelsExemptactivityconcentrations(Bq.g1)andexemptactivities (Bq) are denedinthe IAEABasic SafetyStandards(2)and in the L159 EuratomDirective(3).Theselimits canbeusedbyregulatoryauthorities todene criteria for exemption against formal registrationof the premises and may also be used to develop clear-ance levels for materials leaving the premises. Theexemption levels also apply in the transport regulations.Thecorrect useof theselimitsbyusers is of utmostimportance. Users should refer to the above men-tionedreferences.A1andA2referencetransportactivitiesA1andA2arethemaximumactivities(expressedinTBq) that canbetransportedbyAtypepackages. A1correspondsto radioactivematter inspecial formandA2totheothercases.In the data sheets, the values correspond to values inthe1996editionofTheIAEApublicationRegulationsfor the Safe Transport of Radioactive Materials(4), withwhich the international modal transport authorities(RID, ADR, IMO, ICAO, etc.) areharmonised. Usersseeking further details are referred to the referencedtexts.Thenatureofthemainradiation(5), , e, X, radiationandneutronemissionsaregiven, together with the corresponding energiesexpressedinkeV, andcorrespondingpercentageemis-sions. A maximum of the three most characteristic emis-sionsisgivenforeachtypeof radiation, thecriterionadoptedbeingtherelevanceoftheemissionsfromtheradiationprotectionstandpoint. However, inorder toremedythe restrictive effects of this approach(someradionuclides exhibit multiple emissions, e.g.140La and152Eu), therelative percentageemissions nottaken intoconsiderationareneverthelessgiven.RADIOLOGICALCONTROLExternal exposure risksThefollowingmodesofexposureareconsidered.ContactWhen handling radioactive materials, the operatormaytouchthereceptacle(e.g.beaker, pipette,syringe)containingtheradioactivesubstanceor materialscon-taminated with this substance. The radioactive substancecanalsobecomedepositedontheskin.DistantsourceAll parts of the operators body generally remain dis-tant from the radioactive substances being handled, eventhoughcertain partsof thebodysuch asthe handsandforearms occasionally approach these substances duringhandlingoperationswithorwithoutmanipulators.ImmersioninacloudThistypeofrelativelyinfrequent hazardisencoun-teredwhenhandlinggaseousradioactivesources. Thecorrespondingrisks must betakenintoconsideration,forexample, inlaboratoriesusingcyclotronstomanu-factureshort half-liferadionuclides (e.g.18F,11C,123I).Internal exposure risksThe risks arise from three different possible paths intothehumanbody:Inhalationafterthedispersionofgases, vapoursoraerosolsintheenvironment;Ingestionby contaminatedhands orobjects throughcontactwiththemouth;Transfer through the skin with or without an associa-tedwoundfollowingcontaminationof partsof thebody (which have not been sufciently rapidlydecontaminated) or following simple contact withhighly penetrating radionuclides (e.g. tritium inRADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)11tritiatedwater)orchemicallyaggressivesubstances(acidicsolutions,solvents,etc.).Dose limits for workers(2,6)The occupational exposure of any worker should notexceed the following limits, but may also be subject tomorerestrictivelimitsinappropriatelocal or nationalregulations.aneffectivedoseof100 mSvoveraperiodofveconsecutive years (i.e. 20 mSvper year) averagedoverthisperiod;aneffectivedoseof50 mSvinanysingleyear;an equivalent dose to the lens of the eye of 150 mSvinayear;an equivalent dose to the extremities (hands and feet)ortheskinof500 mSvinayear.ItisnotedthattheIAEA(2)statesthatCompliance withthe foregoingrequirements forapplication of the dose limits on effective doseshall be determined by one of the followingmethods:(a)bycomparingthetotaleffectivedosewiththerelevantlimit,wherethetotal effectivedoseETiscalculatedaccordingtothefollowingformula:ET = Hp(d) + je(g)j,ingestion.Ij,ingestion+ je(g)j,inhalation.Ij,inhalation,whereHp(d)isthepersonal doseequivalent fromexposuretopenetratingradiationduringtheyear.Note that e(g)j,ingestion and e(g)j,inhalation are the com-mittedeffectivedoseperunit intakebyingestionandinhalationfor radionuclidej bythegroupofage g, and Ij,ingestion and Ij,inhalation are the intakes viaingestion or inhalation for radionuclide j during thesameperiod.(b)bysatisfyingthefollowingconditions:Hp(d)/DL + j(Ij,ingestion/Ij,ingestion,L)+ j(Ij,inhalation/Ij,inhalation,L) 1whereDListherelevant doselimit oneffectivedose,andIj,ingestion,LandIj,inhalation,L.aretheannuallimitsonintake(ALI) viaingestionorinhalationofradionuclidej.(c)byanyotherapprovedmethod.Note that the symbols used in the quote are consistentwiththoseusedinthishandbookbut not theoriginalIAEA document. The above quantities are brieyexplainedinScheduleIIofReference2.EXTERNALEXPOSUREAssumptionsX ray, , , eand neutron emissions lead to externalexposuresdependingonthenatureandenergiesofthecorrespondingradiationas well as thepackagingandgeometryof the source. Dependingonthe particularcase being studied, supercial exposures (or skinexposures) denedat a depthof 7 mg.cm2or deepbodyexposures(7)aretakenintoconsideration.Varioushandlingposturesandsituationscommonlyencountered in laboratories are considered. Calculationshave been performed for unique values of source or sol-ution activity; in this way a direct comparison betweenthevaluesobtainedunder different circumstancescanbe made. A nominal activity of 1 MBq has been adoptedfor external exposures, exposures resultingfromcon-tactswith receptaclesandexposuresto distantsources.A nominal value of 1 kBq has been adopted for the caseofskincontaminationduetodropletsand1 kBq.cm2for uniformskin contamination. Exposures due toan innite and uniformly contaminated surface at1 MBq.cm2arealso considered. Data areprovided fordistances of 10 cm and 1 m from the contaminated sur-face for beta and photon radiation for the skin and deeptissue. The quantity adopted for all geometries for tabu-lated data is dose equivalent, expressed in mSv.h1(millisievertperhour).Thehandlingposturesadoptedinthishandbookforsomeoperationswithradionuclidesintheformofun-sealed sourcesmay not actuallyrepresent whatis doneinpractice(e.g. useofasyringeorbeaker). However,the user, by analogy, can transform the values indicatedinto those corresponding to other receptacles of similardimensions, onthebasisthat thesituationsshownarereasonablytypical.Thefollowingcodeshavebeenusedfor thecalcu-lations:MicroshieldVersion4.10hasbeenusedfor andX ray calculations (Grove Engineering, 15215 ShadyGroveRoad,Rockville,USA,1996)Varskinmod2for radiationandVarskinmod2modiedformonoenergetic electrons(J.S.Durham,PacicNorthwest Laboratory, POBox999, Rich-land,Washington99352,USA).Distant (point source) external exposureThecasesof apoint sourceat adistanceof 30 cm(average length of forearm) in air and a penicillin typevial at a distance of 1 m in air(8)are considered success-ively. Inthelattercase, thesourceisrepresentedbyacylinder with a density of 1 g.cm3, 2.3 cm in diameterand 2.5 cmhigh enclosed in a 1.5 mmthick glass(density2.7 g.cm3)envelope.Inthecaseofapoint sourceat 30 cm, thedeeporwhole-body dose equivalent due to X and ray compo-D.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN12nentsisdistinguishedfromthesupercialorskindoseequivalent duetoandecomponents. Thisisdonein order to draw the operators attention to the fact thatthe supercial dose equivalent can be considerablyreduced by interposing a screen with a thicknessequivalent to the maximumrange of the and ecomponents.A deep dose equivalent is given for a vial at 1 m (thiscorresponds tothedistancebetweentheoperator andthebenchortable).Exposures to a uniformly contaminated surfaceExposures duetoauniformlycontaminatedsource(oors) areconsidered. Thecontributions duetobetaradiation and photons are considered separately for dis-tances of 10 cmand1 mfromaninnitelyanduni-formlycontaminatedsurface. This separationenablesusers to make appropriate decisions as to what measure-ment equipment should be used. Pure beta emittersgenerally cannot be detected with gamma detectors.Doseratesat10 cmand1 mareoftensimilarbecausethe increased distance is compensated by theincreased solid angle. Data is quoted for the doseequivalent at depths representingtheskinanddeeptissuerespectively.External contact exposure (receptacles)Thecasesof a50 cm3beaker containing20 cm3ofsolution and a 5 cm3syringe containing 2.5 cm3of sol-ution are considered. The beaker is represented by a cyl-inder with a density of 1 g.cm3, 4 cmin diameter,1.6 cmhighenclosedina 2 mmthickglass (density2.7 g.cm3)envelope.Thesyringeis representedbyacylinder withaden-sity of 1 g.cm3, 1.2 cm in diameter, 2.2 cmhighenclosed in a 1 mmthick plastic (density 1 g.cm3)envelope.Inbothcasesdoseequivalentshavebeencalculatedunder7 mg.cm2atthelevelofthesolution(anarrowindicatesthepositiontakenintoconsideration)(8).Thepositionindicatedcorrespondstothemaximumdoseequivalent towhichanoperator canbeexposedwhen manipulating these receptacles. Attention is drawnto the fact that these drawings, for pedagogical reasons,show the operators hands and ngers as far away fromthesourceaspossible.The dose equivalents depicted take both and componentsintoconsideration. It should, however, benoted that in the case of a beaker (2 mm thick glass),components(otherthanthoseemittedbyradionuclidessuch as42K,90Y and144Pr) can be neglected. In the caseof a syringe (1 mm thick plastic), the contribution canbehighlysignicant(e.g.24 mSv.h1for1 MBq32P).Notethat goodagreement is observedbetweenthevalues quoted here and those found in the literature(912). ray absorption in shielding gives rise to bremsstrah-lung(Xrays). Withhighactivitysourcesbremsstrah-lungradiationcanmake a signicant contributiontodose. Attention is drawn to this in the data sheets. It isfor thisreasonthat Brem. Rad. isindicatedondatasheetscorrespondingtopureemitters(14C,35S,33P,36Cl and45Ca) for which the calculated dose ratesbehind shielding are very low or even zero. These radio-nuclidesareverymuchusedinlaboratories.SHIELDINGOFBETAANDGAMMAEMITTERSTherangeofbetasandelectronsandtheattenuationofXandraysinshieldingmaterialsdependsontheenergiesoftheincidentradiationandthenatureoftheshieldingmaterial.Total absorptionthicknesses have beendeterminedfor anderadiationinglass andplastic(13); thesematerialsarethosemost commonlyusedfor thispur-pose. In the case of and X rays, the rst half-value andtenth-value thicknesses of lead and steel (attenuating theincidentradiationby afactorof2 and10respectively)aregiven.Attention is drawn to the fact that some radionuclidessimultaneously emit signicant lowand high energycomponentsfor whichrst half-valueandtenth-valuethicknessesmay beconsiderablylessthan secondhalf-value and tenth-value thicknesses.123I is an example butthedataprovidedheredonotcoverthissituation.CONTAMINATIONContact exposure due to external skincontaminationTwo situations have been considered to illustratebodycontamination.Firstly,exposureduetoanexten-sive uniformly spread out contamination of theskin(9,14,15)is considered and secondly, the projection ofa 0.05 cm3droplet of a radioactive substance. The drop-let is represented by a cylinder with a density of1 g.cm3, acrosssectional areaof1 cm2andaheightof0.5 mm(8).Doseequivalent valueshavebeencalculatedfor anaverage 70 m basal layer depth. At this depth the maincomponent of thedoseresultingfromsupercial con-taminationof theskinisduetoraysandelectronsfrom the radionuclide; the contribution to the dose isgenerallyjustafewpercent. Comparisonbetweenthevalues due toa uniform(innitelythin) deposit andthose due to a droplet highlights the effects of attenu-ation in tissue. It is assumed here that penetration of thecontaminationintheskincanbeneglected.Decay productsDecaying radionuclides are generally treated asfollows:RADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)13radionuclides (parentprogeny) couples are assumedtobeinequilibrium;calculationsare performedfor anominal activityofthe parent nuclide (e.g. 1 kBq.cm2for uniformskincontamination);parentprogeny radionuclide decay schemes arenormally covered in a single sheet, but when physi-cal separation of the constituents is possible (e.g. byelution), progenyproductsaretreatedinindividualsheets. The99Mo99mTc couple is an example of this.The reader will nd both99Mo99mTc and99mTcsheets.Decay of heavy elementsIn the case of heavy element decay chains (e.g. lead,radium, uranium, plutonium and americium), where theparent andprogenyarenot necessarilyinequilibrium(e.g. after chemical separation or extraction of anelement) the respective activities of each of the progenyin the chain will depend upon the age of the sample. Itis not possible to cover all situations likely to beencountered but the Appendix to this handbook includesselected major heavy element decay chains and theactivitiesofrespectiveprogenyinthechainaregivenas a fraction of the parent activity as a function of time(agesinceseparation)for0.1day,1day,10days,100days, 1 year, 10 years and 100 years. The parent radio-nuclides for which this information is provided aremarked!!inthemaindatasheets, includinganindi-cationoftherstandlastelementswithinthechains.A similar approach can be adopted if data on naturaluranium or re-constituted natural uranium are requiredbytakingintoaccounttheisotopiccomposition.The data in the Appendix are derived using RadDecayversion1.13(16).Derived surface contamination limitsThe derived surface contamination limit (DSCL) is anon- regulatory quantity enabling exposure risks due toremovable and/or xed surface contamination to bequantied. Exposure to the DSCL leads to a dose whichdoes not exceed the maximumannual occupationalexposurelimit(correspondingto2000workinghours).Amodel isusedtodeterminetheDSCLvaluescorre-spondingtothe different radionuclides dealt with(17).This model takes different modes of exposure and trans-ferparametersintoconsideration. Thesedataaregivenfor completeness and the values do not supersede limitsimposed by regulations, which are invariably muchlower.Occupationalexposuresmayresultfrom:transferofsurfacecontaminationtotheatmosphereleadingtointernalexposurethroughinhalationtransfer of surface contaminationto the organismthroughingestiontransfer of surface contamination to the skin leadingtoexternalextremityexposureswhole-bodyexposureduetosurfacecontamination.TheDSCLisdenedbythefollowingequation:1/DSCL = 1/Asatm + 1/Asingestion+ 1/Asskin + 1/AssurfwhereAsjis theactivityper unit surfaceareaof thecontaminated zone leading to annual limits due to eachofthefourmodesofexposure(consideredseparately).Limitsof20 mSv.y1and500 mSv.y1areconsideredfor wholebodyexternal exposureandskinexposure,respectively. The most restrictive ALIinhalationandALIingestion values calculated for 20 mSv.y1are used inthe following derivations of surface activity for limitinginternalcontamination.CalculationofAsatmAsatm is the value of the activity per unit surface areaof the contaminated zone which leads to an ALIinhalationdose with an atmosphericre-suspension factor, Tatm, of10-4m1and an annual occupational exposure of 2000 hwitharespiratoryvolumerate,R,of1.2 m3.h1.Asatm(Bq.cm2)isgivenbythefollowingequation:Asatm = ALIinhalation/(Tatm 2000 R 104)CalculationofAsingestionAsingestionisthevalueoftheactivityperunitsurfacearea of the contaminated zone which leads to anALIingestiondosewithanorgantransferfactor, Tingestion,of 1 cm2.h1andanannual occupational exposureof2000 h. This component may simulate, for example, theriskduetoachronicexposureataworkingpost.Asingestion(Bq.cm2) is given by the followingequation:Asingestion = ALIingestion/(2000 Tingestion)CalculationofAsskinAsskin is the value of the activity per unit surface areaof the contaminated zone leading to an annual skin doseof 500 mSv for an occupational exposure of 2000 h andaskintransfer factor, Tskinof 0.1. It is assumedthatcontaminationiseliminatedonadailybasiswhentheuser washes on leaving the working zone. Neither radio-activedecaynortherenewalofskincells(whichcon-tribute towards eliminating radioactivity) are takenintoaccount.Asskin(Bq.cm2) isgivenbythe followingequation:Asskin = 500/(Tskin 2000 Dp)whereDp(mSv.h1)isaconversioncoefcient givingD.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN14thedoserateintissuebeneath7 mg.cm2for askincontaminationof1 Bq.cm2(14,15).CalculationofAssurfAssurf(Bq.cm2)isthevalueoftheactivityperunitsurface area of the contaminated zone leading toaneffectivedoseequivalent of20 mSvforanoccupationexposureof2000 h.Assurf(Bq.cm2)isgivenbythefollowingequation:Assurf = 20/(2000 Dfloor)where Door (mSv.h1) is a conversion coefcient givingthe effective dose equivalent 1 m above a oor innitelyanduniformlycontaminatedat1 Bq.cm2(14).AlphaemittersThe DSCL value corresponding to most radionuclidesliesbetween 1 Bq.cm2and105Bq.cm2,and, ingen-eral, is of the order of 100 Bq.cm2. In the case of alphaemitters, themodelcanleadtoveryrestrictivevalues;a lower limit of 0.04 Bq.cm2has beenimposedforalphaemitters.Determination of removable and xedcontamination valuesDSCLvalues enablederived limitsto bedeterminedfor removable(or non-xed) andxedcontamination.The above limits enable the potential risk to users fromsurfacecontaminationtobeassessedtogetherwiththemostappropriatemeansfordecontamination.Inthecaseofremovablecontamination, thederivedlimit is denedas beingequivalent to1/10thof theDSCL value of the radionuclide considered (this allowspossibleoccupational exposuresofotheroriginstobetakenintoconsideration).Inthecaseofxedcontamination,thederivedlevelisdenedasthevaluecorrespondingtoawhole-bodyexposurefromauniformly contaminatedoorequival-entto1/10thoftheannualexposurelimitsof20 mSv.The DSCL value for xed contamination alwaysexceeds the value for removable contamination. Forsomeradionuclidessuchaspurebetaoralphaemit-ters, the ratio of the two values can be highly signicant(radiation from the oor being negligible). In this hand-book, the DSCL value for xed contamination is set at amaximum of 100 times the derived limit for removablecontamination (e.g. see14C on page 24). Regulations donot usuallyinclude specic limits for xedcontami-nationsinceitseffectistakenintoaccountinexternalradiationlevels.Contamination controlThe level of removable contamination of workingzonesandmaterials mustbekeptas lowasreasonablypracticable by appropriate maintenance and cleaningoperations. When accidental contamination (even ofvery low level) occurs, decontamination must be carriedoutasquicklyaspossible.Detection probesSurface contamination due to many of the radio-nuclidescoveredinthesesheetscanbedetectedwithsoft, , ,Xrayorprobes.Preferences given to particular types of probe orinstrument areindicatedfor eachtypeof radiation. Asingle + meansthat such a type of probeor instrumentcan possibly be used, double ++ means that this type ofprobe or instrument is recommended, whilst the absenceof a + sign means that that type of probe or instrumentisnotsuitable. Absenceofa +signinanyboxmeansthat direct measurement is inappropriate and a wipe test,in association with a suitabledetection system, such asliquid scintillation methods, would be appropriate. Thisappliesonlytotritiuminthishandbookbut thesametechniquecanbeappliedwithadvantagetolowlevelsof contamination of other radionuclides, especially thosewithlowpenetrationemissions.INTERNALEXPOSURECommitted effective dose per unit intakeInternal exposures resulting from ingestion andinhalation are evaluated with the dose coefcients,e(g)ingestionande(g)inhalation, expressedinSv.Bq1, andidentically given by the ICRP(18), the IAEABasicSafetyStandards(2)andtheL159EuratomDirective(3).Listedvaluestaketheageofexposedindividualsintoaccount (1 year, 12 years, 27 years, 712 years, 1217years and17 years)aswell astheir status(publicor occupational exposure). In this handbook only occu-pationalexposuresareconsidered.The committed effective dose per unit intake viaingestionis givenfor different gut transfer factor, f1,values. Thisfactor quantiestheproportionof intaketransferred to body uids in the gut and depends on thechemicalformoftheradionuclide.The committed effective dose per unit intake via inha-lationisgivenfor threedefault lungabsorptiontypes(fast, moderate, slow). These coefcients depend on thechemical formand particle size of the aerosol. It isrecalledthatparticlesizeisquantiedbyaerodynamicmedian activity diameter (AMAD) parameters. Inha-lationcoefcients aregivenfor 1and5mAMADvalues. Indication of the different forms for each nuclidethat correspond to different gut transfer factors and lungabsorptiontypesaregiveninthedatasheets. Insomecases, forexamplephosphorusandsulphur, wherethenuclide mayformpart of the anion, the gut transferfactoror lungabsorptiontypesmaybepredominantlyRADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)15determined by the associated cation. These are indicatedinthedatasheets.Annual Limits on Intake (ALI)AnnualLimitsonIntakebyingestionandinhalation(Iingestion,Land Iinhalation,L) are given in order to assistusers who are not familiar with the dose per unit intakecoefcients discussed above. Iingestion,L and Iinhalation,L arecalculatedusingthefollowingrelationship(19):IL = DL/e(g)where DLis the average annual limit of 20 mSv. ILvaluescanbeconsideredtobeALIvalues.ALIingestionand ALIinhalationvalues are given inthedata sheets for an average annual 20 mSv limit and themostrestrictive e(g)values,respectively.They arecal-culated values(19), not values given by ICRP, and usersshould be aware of this. The references should be con-sulted,whereappropriate,forfurtherinformation.The highest dose organVarious metabolic and dosimetric models haveenabledretentionandexcretionfunctions after intakeby inhalation by Reference Man to be established(1921).These models have also enabled committed whole-bodyand organ doses to be determined. Some organs prefer-entiallyconcentrate particularradionuclides. Therefore,the data sheets indicate which is the highest doseorgan(e.g.thethyroidinthecaseofiodinenuclides).Thehighest doseorgandependsonphysicochemicalform and whether intake results from ingestion or inha-lation. Only inhalation (for an AMAD of 1 m) is con-sideredinthishandbook. It shouldalsobenotedthatthesefunctionsdependontheclearancetimefromthepulmonaryregiontotheremainderofthebody(F, M,S). Therefore, the highest dose organ may also dependon the elimination class.90Sr is an example; dependingonwhether For Sclassesareconsideredeither bonesurface or lungs can be considered as being the highestdose organ. However, for some chemical forms theassociatedanionor cationmaybemoreimportant inthiscontext.GeneralInternal exposure values are determined using variousestablished metabolic and dosimetric models andhypotheses, which are subject to reviewby ICRP.Interpretation of the results of these analyses should bedonebyspecialists.MAXIMUMRECOMMENDEDACTIVITIESOperators or competent radiation protection personneloften require order-of-magnitude estimates on themaximumactivitiesthatcanbehandledwithavailableequipment (chemical benches, fume hoods, gloveboxes)oringivenworkingareas(controlledorsuper-visedareas).Whilstthepurposeofthishandbookistoprovidedatarather thanadviceonpractices, it isfeltappropriate to include information on maximumrecommendedactivities.Thedataprovidedareappropriatetolowandinter-mediate levellaboratories and notto highlevel labora-tories, where extensive professional radiation protectionexpertisewillbeavailable.Calculation modelsThe maximum activity (Ao) corresponding to a parti-cular nuclide and handling situation is characterised bythe potential risk associated with handling specicnuclides. External exposureduetoandradiationcomponents and the re-suspension of the nuclide in theatmospherearetakenintoconsideration.Ao(Bq) is determinedfromthefollowingrelation-ship:1/Ao = 1/Abeta + 1/Agamma + 1/Avolatilewhere Abeta(Bq) and Agamma(Bq) represent themaximumactivitiesdeterminedforapointsourceatadistance of 30 cm in air. These activities are calculatedforthefollowingdoseratelimits:250 Sv.h1under7 mg.cm2forbetacomponents,10 Sv.h1forgammacomponents.Avolatile(Bq)isrelatedtopotential atmosphericcon-taminationrisksdirectlydependentonthevolatilityoftheradioactiveproduct.Infreeair,Avolatileisgivenbytheexpression:Avolatile = 102ALIinhalation/k,wherekisthevolatilityfactor.It shouldbenotedthat themaximumrecommendedactivities giveninthesesheets havebeendeterminedusingthemost restrictiveALIinhalationvaluesdescribedabove; k values, related to the volatility of the product,aredenedasfollows:k = 1: gases, substances with high saturation vapourpressures of about 1 bar at 20C, substances pen-etratingtheskin,particlessmallerthan5 m.k = 0.1:substanceswith saturationvapourpressuresof about 0.1 bar at 20C, particles larger than 5 m.k = 0.01: lowvolatility substances with saturationvapour pressures of about 0.01 bar at 20C(e.g.water).k = 0.001: non-volatile substances with saturationvapourpressureslessthan0.01 barat20C.Dependence of maximum recommended activitieson equipment and working areasThefollowing additionalrules areused todetermineD.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN16therecommendedlimits for benches, fumecupboardsandgloveboxes:It is forbidden to manipulate highly volatile sub-stances(k 0.01)orradionuclideswithALIinhalationvalues lower than 1000 Bq on chemical benchesbecauseevenalowlevel contaminationcouldleadto a signicant ALIinhalation fraction that would be dif-culttodetect.Manipulating substancesunder afume hoodis con-sideredtoincreaseprotectionbyafactor of 10incomparisonwithanopenbench.Manipulating substances in a glove box is consideredto increase protection by a factor of 100 in compari-sonwithfumehoods.Maximum recommended levels of activity in super-vised areas are nominally 3/10 of those in controlledzones(thisapproximatelyrepresentstherespectiveexposurelimits denedfor theseareas). However,theinstallationof gloveboxesinsupervisedzonesis generally deprecated; the level of protectionaffordedbyagloveboxisconsideredincompatiblewith the denition of such zones. It should be notedthatthefactorof3/10maybemaskedbyroundingthedatatoonesignicant gure; roundinginanyother way may imply an unjustied degree of accu-racy in the models used for deriving the rec-ommendedlevelsofactivity.LimitationsAreacontrolThevaluesindicatedinthesesheetsapplymainlytothesupervisedandcontrolledareas of lowandinter-mediateactivitylaboratories. Maximumrecommendedactivitieshavefurtherbeenlimitedto:Group1(red)0.5 GBqGroup2(orange)5 GBqGroup3(yellow)5 GBqGroup4(green)5 GBqGroup5(blue)50 GBqTheselimitshavebeenimposedbecausesuchlabora-toriesarenot generallyequippedwitheither ameansforcontinuouslymonitoringtheworkingenvironment,or for rejecting gases at a sufcient height to ensure thatnorecyclingtakesplace.It should be noted that values calculated in com-pliancewiththeserulesareguidevaluesandareonlyindicativesinceothernon-quantiableparameterssuchas workingmethods andhumanfactors must alsobetakenintoaccount. Nevertheless, it hasbeenobservedthat whenpracticesareperformedinaccordancewiththese simple rules, only very low levels of atmosphericcontaminationandexposureoccur.The maximum recommended levels for elemental trit-ium (3H), tritiated water and37Ar have been deliberatelyreduced because of the difculty of detecting the corre-sponding surface or atmospheric contamination. Thisfactor can be modied in particular situations,depending on survey andcontrol frequencies. In thecase of iodine isotopes (123I,125I,131I), the existence ofparticularlyunstable states (withthe possibilityof I2release) hasbeenconsidered. Thecorrespondinglimi-tationsareconsequentlymuchmorestringent.RadiationcontrolHandledorstoredactivityvaluesmust complywithexternal exposure limits in situations where the externalradiation hazard may be more restrictive than theinternal radiation hazard. Attention is drawn to this factinthedatasheets bytheremarkSubject toexternalexposure requirements which maybe more restrictive.Storedactivities mayexceedmaximumrecommendedactivities by a factor of 10, subject to any limits imposedbylocalornationalregulations.Inparticular cases, listedvalues maybe variedinlocal regulations, based upon assessments by pro-fessionalradiationprotectionspecialists.DESCRIPTIONOFDATASHEETSGeneralIndividual data sheets provide data in ve main areas,namely basic radionuclide date, external exposure, con-tamination, internal exposure and maximum rec-ommended activities in laboratory situations. These aredividedintophysicalcharacteristics, (halflife, specicactivityanddecayscheme, A1andA2referencetrans-port activities, exemption levels, data for externalexposure for ve different geometries, external andinternal exposure limits, appropriate contaminationdetectionprobesandhalf-valueandtenth-valueshield-ingthicknesses. The maximumactivities that canbehandled on benches, under fume hoods or in gloveboxesarealsogiven.Thehighestdoseorganisindi-cated, even where this is the whole body. As describedearlier the data sheets are coloured red, orange, yellow,greenor blue, indicating, indescendingorder of risk,thelevelofriskposedbytheparticularradionuclide.GLOSSARYActivityThenumberofnucleartransformationsoccurringinagivenamount of radionuclideper unit time. TheSIunit of activityisthereciprocal second, s1, withthespecialnamebecquerel(Bq).RADIONUCLIDEANDRADIATIONPROTECTIONDATAHANDBOOK2ndEdition(2002)17Annual limit of intakeThe intake by inhalation or ingestion of a given radio-nuclideinayear bytheReferenceManwhichwouldresult inacommitteddoseequal totherelevant doselimit.BremsstrahlungXrays producedbydecelerationof particles inmaterials.Committed equivalent doseFollowing an intake to the body of a radioactivematerial, the time integral of the equivalent dose rate iscalled the committed equivalent dose. If the integrationtimefollowingtheintakeisnotspecied,itisimpliedthatthevalueis50yearsforadults.Equivalent doseTheequivalentdose,HT,RisdenedasHT,R = WR DT,RREFERENCES1. Delacroix, D., Guerre, J. P. andLeblanc, P. Radionuclides andRadioprotection. (FrenchAtomicEnergyCommission),(June1994).2. IAEA. International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources.SafetySeriesNo.115,(Vienna:IAEA)(1996).3. EURATOMDIRECTIVE;L159,13May1996.4. IAEA. Regulations for the Safe Transport of Radioactive Material. 1996 Edition. Safety Standards Series No.ST1/Requirements(Vienna:IAEA)(1996).5. Lagoutine,F.,Coursol,N.andLegrand,J.TablesdesRadionucleides.CEA-ORIS,4vol,(19831987).6. ICRP. 1990 Recommendations of the International Commission on Radiological Protection. Publication 60, (Oxford:Pergamon)(1990).7. ICRP.DataforUseinRadioprotectionagainstExternalRadiation.Publication51(Oxford:Pergamon)(1987).8. Delacroix, D., Chazot, C. andGuerre, J. P. CalculdesDebitsdeDoseet enFonctiondelaGeometriedelaSource.CE.ReportDSCE/SRI-A/93-362,(April1993).9. Takaku, Y. and Kida, T. Radiation Dose to the Skin and Bone of Fingers from Handling Radioisotopes in a Syringe. HealthPhys22,295297(1971).10. Henson,P.W. RadiationDosetotheSkininContactwithUnshieldedSyringesContainingRadioactiveSubstances.Br.J.Radiol.46,972977(1973).11. Perotin, J. P. and Goubert, J. Evaluation des Risques dIrradiation des Mains dans un Laboratoire de Controle Radiopharma-ceutique.D.CEA-Saclay.ReportSPR/SRI(1979).12. Schmidt, W., Nowotny, R., Kletter, P. and Frisschauf, H. Radiation Exposure due to99mTc and131I Manipulated in Syringes.J.Nucl.Med.4,389391(1979).13. Moreau, A. LaRadioprotectiondanslesLaboratoiresdeFaibleetMoyenneRadioactivite. CEA-Saclay. ReportSPR/SRI,1981.14. Kocher, D. C. and Eckerman, K. F. Electron Dose Rate Conversion Factors for External Exposure of the Skin from UniformlyDepositedActivityontheBodySurface.HealthPhys.53(2)135141(1987).15. Piechowski,J.,Menoux,B.,Chaptinel,Y.andDurand,F.DosimetrieetTherapeutiquedesContaminationsCutanes.CEAReport5441(1988).16. RadDecayVersion1.13.GroveEnginering(Rockville,Maryland,USA)(1996).17. Delacroix, D., Guerre, J. P. andLeblanc, P. Determinationdeslimitesdecontaminationsurfaciquepour lesprincipauxradionucleides.CEA-Saclay.ReportDSCE/SRI,January1992.whereDT,Ristheabsorbeddosedeliveredbyradiationtype R averaged over a tissue or organ T and WR is theradiationweightingfactor for typeRradiation. Whenthe radiationeldis composedof different radiationtypes,theequivalentdoseisHT = RWR DT,R.Effective doseThe quantity E, dened as a summation of the tissueequivalent doses, each multiplied by the appropriatetissueweightingfactor(E = TWT HTwhereHTistheequivalent dose in tissue T and WT is the tissue weight-ing factor for tissue T). From the denition of equivalentdoseitfollowsthatE = TWTRWR DT,R.Radioactive half-lifeTime required for a radioactive substance to lose 50%ofitsactivitybyradioactivedecay.Half-value and tenth-value thickness (or layer)The thickness of material necessary to reduce theintensity of X or gamma radiation by a factor of 2 and10,respectively.D.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN1818. ICRP.DoseCoefcientsforIntakesofRadionuclidesbyWorkers.Publication68(Oxford:Pergamon)(1994).19. ICRP. Individual Monitoring for Internal Exposure of Workers, Replacement of ICRP Publication 54. Publication 78 (Oxford:Pergamon)(1997).20. ICRP. LimitsforIntakesof RadionuclidesbyWorkers. Publication30(Parts14andSupplements) (Oxford: Pergamon)19791988).21. ICRP.IndividualMonitoringforIntakesofRadionuclidesbyWorkers:DesignandInterpretation.Publication78(Oxford:Pergamon)(1998).RADIONUCLIDEANDRADIATIONPROTECTIONDATA(2002)19RadiationProtectionDosimetryVol.98,No.1,pp.1920(2002)NuclearTechnologyPublishingTABLEOFRADIONUCLIDESLISTEDNuclide Symbol PageTritium (3H1) 21Beryllium-7 (7Be4) 22Carbon-11 (11C6) 23Carbon-14 (14C6) 24Nitrogen-13 (13N7) 25Oxygen-15 (15O8) 26Fluorine-18 (18F9) 27Sodium-22 (22Na11) 28Sodium-24 (24Na11) 29Aluminium-26 (26Al13) 30Silicon-31 (31Si14) 31Phosphorus-32 (32P15) 32Phosphorus-33 (33P15) 33Sulphur-35 (35S16) 34Chlorine-36 (36Cl17) 35Argon-37 (37Ar18) 36Argon-41 (41Ar18) 37Potassium-40 (40K19) 38Potassium-42 (42K19) 39Potassium-43 (43K19) 40Calcium-45 (45Ca20) 41Calcium-47/Scandium-47 (47Ca20/47Sc21) 42Scandium-46 (46Sc21) 43Scandium-47 (47Sc21) 44Vanadium-48 (48V23) 45Chromium-51 (51Cr24) 46Manganese-52m (52mMn25) 47Manganese-52 (52Mn25) 48Manganese-54 (54Mn25) 49Manganese-56 (56Mn25) 50Iron-52 (52Fe26) 51Iron-55 (55Fe26) 52Iron-59 (59Fe26) 53Cobalt-56 (56Co27) 54Cobalt-57 (57Co27) 55Cobalt-58 (58Co27) 56Cobalt-60 (60Co27) 57Nickel-63 (63Ni28) 58Nickel-65 (65Ni28) 59Copper-64 (64Cu29) 60Copper-67 (67Cu29) 61Zinc-65 (65Zn30) 62Gallium-66 (66Ga31) 63Gallium-67 (67Ga31) 64Gallium-68 (68Ga31) 65Arsenic-73 (73As33) 66Arsenic-74 (74As33) 67Arsenic-76 (76As33) 68Arsenic-77 (77As33) 69Selenium-75 (75Se34) 70Bromine-77 (77Br35) 71Bromine-82 (82Br35) 72Krypton-81 (81Kr36) 73Krypton-83m (83mKr36) 74Krypton-85 (85Kr36) 75Krypton-85m (85mKr36) 76Rubidium-86 (86Rb37) 77Strontium-85 (85Sr38) 78Strontium-89 (89Sr38) 79Strontium-90/Yttrium-90 (90Sr38/90Y39) 80Yttrium-90 (90Y39) 81Yttrium-91 (91Y39) 82Zirconium - 95 / Niobium - 95 (95Zr40/95Nb41) 83Molybdenum- 99/ Technetium- 99m (99Mo42/99mTc43) 84Technetium -99m (99mTc43) 85Technetium -99 (99Tc43) 86Ruthenium - 103 / Rhodium - 103m (103Ru44/103mRh45) 87Ruthenium-106/Rhodium-106 (106Ru44/106Rh45) 88Palladium-103/Rhodium-103m (103Pd46/103mRh45) 89Silver-110m (110mAg47) 90Silver-111 (111Ag47) 91Cadmium-109 (109Cd48) 92Indium-111 (111In49) 93Indium-113m (113mIn49) 94Indium-115m (115mIn49) 95Tin-125 (125Sn50) 96Antimony-122 (122Sb51) 97Antimony-124 (124Sb51) 98Antimony-125/Tellurium-125m (125Sb51/125mTe52) 99Antimony-126 (126Sb51) 100Tellurium-123m (123mTe52) 101Tellurium-125m (125mTe52) 102Tellurium-132/Iodine-132 (132Te52/132I53) 103Iodine-123 (123I53) 104Iodine-124 (124I53) 105Iodine-125 (125I53) 106Iodine-129 (129I53) 107Iodine-131 (131I53) 108Iodine-132 (132I53) 109Iodine-133 (133I53) 110Xenon-133 (133Xe54) 111Caesium-131 (131Cs55) 112D.DELACROIX,J. P.GUERRE,P.LEBLANCandC.HICKMAN20Caesium-134 (134Cs55) 113Caesium-137/Barium-137m (137Cs55/137mBa56) 114Barium-133 (133Ba56) 115Barium-140/Lanthanum-140 (140Ba56/140La57) 116Lanthanum-140 (140La57) 117Cerium-139 (139Ce58) 118Cerium-141 (141Ce58) 119Cerium-143 (143Ce58) 120Praseodymium-143 (143Pr59) 121Praseodymium-144 (144Pr59) 122Promethium-147 (147Pm61) 123Samarium-153 (153Sm62) 124Europium-152 (152Eu63) 125Europium-154 (154Eu63) 126Europium-155 (155Eu63) 127Europium-156 (156Eu63) 128Erbium-169 (169Er68) 129Thulium-170 (170Tm69) 130Thulium-171 (171Tm69) 131Ytterbium-169 (169Yb70) 132Rhenium-186 (186Re75) 133Rhenium-188 (188Re75) 134Iridium-192 (192Ir77) 135Gold-198 (198Au79) 136Mercury-197 (197Hg80) 137Mercury-203 (203Hg80) 138Thallium-201 (201Tl81) 139Thallium-204 (204Tl81) 140Lead-210 (210Pb82) 141Lead-214 (214Pb82) 142Bismuth-207 (207Bi83) 143Bismuth-210 (210Bi83) 144Bismuth-214 (214Bi83) 145Polonium-210 (210Po84) 146Radium-226 (226Ra88) 147Thorium-231 (231Th90) 148Thorium-234 (234Th90) 149Protactinium-234 (234Pa91) 150Protactinium-234m (234mPa91) 151Uranium-233 (233U92) 152Uranium-234 (234U92) 153Uranium-235 (235U92) 154Uranium-238 (238U92) 155Neptunium-239 (239Np93) 156Plutonium-238 (238Pu94) 157Plutonium-239 (239Pu94) 158Plutonium-240 (240Pu94) 159Plutonium-241 (241Pu94) 160Americium-241 (241Am95) 161Americium-243 (243Am95) 162Curium-244 (244Cm96) 163Californium-252 (252Cf98) 164

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