review of ieaf-2001 cross section data libraries for ifmif activation and transmutation analyses

Forschungszentrum Karlsruhein der Helmholtz-Gemeinschaft Association FZK-Euratom

Review of IEAF-2001 Cross Section Data Libraries for IFMIF Activation and

Transmutation Analyses

U. Fischera), A. Konobeyeva), Yu. Korovinb), D. Leichtlea), U. v. Möllendorffa), P. Pereslavtseva), I. Schmucka),

S. P. Simakova), P. P. H. Wilsonc)

a)Association FZK-Euratom, Forschungszentrum Karlsruheb) Institute for Nuclear Power Engineering (INPE), Obninsk, Russia

c) University of Wisconsin, Madison, USA

IAEA TC Meeting, Karlsruhe, October 4-6, 2005


U. Fischer, Review IEAF-2001 Data Libraries IAEA TC Meeting, Karlsruhe, October 4-6, 2005

• History– Collaboration of Forschungszentrum Karlsruhe (FZK) and Institute for

Nuclear Power Engineering (INPE), Obninsk– 1997-1999: Activation data files for Z=6-84 target nuclides based on EAF-97

MeV data for E<20 MeV – 2000: Data file completion with Z<6 nuclides; addition of MF=2 resonance

parameter skeleton– 2001: IEAF-2001 based on EAF-99 data for E<20 MeV, processing & first

applications tests. – 2002: Validation analyses, IFMIF applications– 2003: IEAF-2001 group data library for FISPACT

• IEAF-2001 ObjectiveDevelopment of nuclear data base required for transmutation activation analyses of IFMIF D-Li neutron source (En > 20 MeV) and other intermediate energy applications (En<150 MeV)



• Pre-equilibrium nucleon emission– Modified geometry dependent hybrid (GDH) model– Pre-compound cluster (d, t, 3He, ) and -ray emission– Code ALICE/ASH (INPE Obninsk)

• New approach for light mass nuclei (Z6) based on diffraction theory – A. Konobeyev et al., Nucl. Sci. Eng. 139, 1-23 (2001)

• Adoption of EAF-99 data below 20 MeV– J.-Ch. Sublet, J. Kopecky, R. Forrest, European Activation File EAF-99, Report UKAEA

FUS 408, 1998

Evaluation MethodologyYu. Korovin, A. Yu. Konobeyev, P.E. Pereslavtsev et al, Journ. Nucl. Sci. Techn., Suppl. 2, p. 68-71 (August 2002)



• Neutron energy range: 10-5 eV En 150 MeV

• 679 target nuclides: Z=1 (hydrogen) to 84 (polonium) 134.000 reaction cross-sections

• Standard ENDF-6 data format – MT=5 (n, anything) data representation– Lumped MT=5 excitation function stored in MF=3 section– Reaction product yield vectors in MF=6 section (LAW=0) – MF=2 resonance parameter skeleton to enable processing with NJOY

ENDF Data File Features



• GENDF group data library G-IEAF-2001/XS-256 – Generated with NJOY/GROUPR based on version 99.0 – Modifications required

• GENDF data format (minor changes; ZAT)• NJOY/GROUPR:– Minor changes for processing of MT=5, MF=6 (LAW=0)– Major changes for automated processing of all sub-sections

• 256 energy group structure– 175 VITAMIN-J energy groups below 20 MeV– 1 MeV energy bins for 20 En 50 MeV, 2 MeV bins above

• Flat weighting spectrum

Data File Processing



• For use with ALARA activation code– Analytical and Laplacian Adaptive Radioactivity Analysis – Next generation activation code developed at University of Wisconsin-Madison (P. Wilson) – Capable of handling an arbitrary number of reaction channels (282 needed for IEAF-2001 !)– Reactions defined entirely by the library (no fixed reaction tables)

• Cannot be used by standard activation codes– FISPACT (UKAEA Culham), ANITA (ENEA), ….

Use of fixed reaction tables

Group Data Library G-IEAF-2001/XS-256



• Required for standard activation codes:– Convert MT=5 (MF3/MF6) data to nuclide production cross-section data (MF3)

• Non-standard MT numbers (181) • ENEA Bologna, IEAF-2001 for ANITA code

– Assume MT=5 as pseudo fission reaction• FZK, Karlsruhe, for FISPACT code

• G-IEAF-2001/PY-256– MT=5/MF=3: pseudo fission product cross-section

• No other cross-section • MT=5/MF=6: pseudo fission product yields• Calculated on the basis of G-IEAF-2001/XS-256 data • Stored on MF=8 as independent fission product yield data (MT=454)

Group Data Library G-IEAF-2001/PY-256



Group Data Library G-IEAF-2001/PY-256

Changes applied Comments

Declare MT=5 as fission reaction. Required for handling the MT=5 reaction in the same way as fission in the code.

Declare all 679 nuclides as fissionable. Required to take into account all target nuclides given on the IEAF-2001 data files

Add 256 energy group structure. Required for IEAF-2001 cross-sections data with upper energy limit of 150 MeV

Weigh the energy-dependent product yields with the normalised neutron spectrum in 256 energy groups.

Required to provide the correct effective cross-section when multiplied by the MT=5 cross-section and collapsed to one energy group.

Major FISPACT modifications



(2) Integral activation experiment in white neutron field produced by 40 MeV deuteron beam on thick Li-target ("IFMIF-like" neutron spectrum)

• SS-316 steel, F82H steel, V and V-4Ti-4Cr alloy samples• U. v. Möllendorff et al, Report FZKA 6764, 2002 ALARA/G-IEAF-2001/XS-256 vs. experiment Testing/qualification of data

Testing and Validation (1)ALARA-calculations using G-IEAF-2001/XS-256 data(1) Fusion activation benchmark: Irradiation of reduced activation steel Eurofer in first wall of Fusion Demo reactor ALARA/G-IEAF-2001/XS-256 vs. FISPACT/EAF-99

(E 20 MeV: IEAF-2001 = EAF-99) Validation of procedure



ALARA/IEAF-2001 vs. FISPACT/EAF-99

10-2 10-1 100 101 102 103 104 105 106 107 108 109 1010107

108

109

1010

1011

1012

1013

1014

1015

Eurofer activation in Demo first wall

106y104y1m 105y

53Mn

10y 103y100y1y30d1d1h

55Fe

3H

14C

Total Activity

Act

ivity

, B

q/kg

Time after shutdown, hours

FISPACT/EAF-99: dashed with symbols ALARA/IEAF-2001: straight lines



ALARA/IEAF-2001 vs. FISPACT/EAF-99

10-2 10-1 100 101 102 103 104 105 106 107 108 109 101010-7

10-6

10-5

10-4

10-3

10-2

10-1

100

101

102

103

104

105

54Mn

56Mn

106y104y1m 105y

26Al

10y 103y100y1y30d1d1h

94Nb

60Co

Total Dose Rate

Con

tact

Dos

e R

ate

[Sv/

h]

Time after irradiation [hours]

FISPACT/EAF-99: dashed with symbols ALARA/IEAF-2001: straight lines

Eurofer activation in

Demo first wall



ALARA/IEAF-2001 vs. Experiment

0.01

0.1

0.5

1.0

10.S

c-46

Sc-

48V

-48

Cr-

48C

r-49

Cr-

51M

n-52

Mn-

54M

n-56

Fe-5

2Fe

-59

Co-

55C

o-56

Co-

57C

o-58

Co-

60C

o-61

Ni-5

6N

i-57

Y-87

Y-87

mY-

88Zr

-86

Zr-8

8Zr

-89

Zr-9

7N

b-90

Nb-

92m

Nb-

95N

b-95

mN

b-96

Mo-

90M

o-93

mM

o-99

Tc-9

9m

2.0

93mMo61Co55Co56Co

52Mn48V

48Cr

87mY

87Y

86Zr 97Zr

Cal

cula

tion/

Exp

erim

ent

SS-316 IFMIF activation experiment



ALARA/IEAF-2001 vs. Experiment

Ca-47 Sc-43 Sc-44Sc-44mSc-46 Sc-47 Sc-48 V-48 Cr-51 Mn-52Nb-92m0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

1.6

1.8

2.0

- V - V-4Ti-4Cr

C

alcu

latio

n/E

xper

imen

t

Radioactive Nuclide



(1) FISPACT/G-IEAF-2001/PY-256 vs. FISPACT/EAF-99 using 175 group data G-IEAF-2001 data cut-off at 20 MeV (E 20 MeV: IEAF-2001 = EAF-99) Different computational procedures and group data, identical underlying

neutron cross-sections. Agreement pre-requisite for application > 20 MeV

(2) FISPACT/G-IEAF-2001/PY-256 vs. ALARA/G-IEAF-2001/XS-256 benchmark calculations

Validation of new procedure for whole energy range Use of v. Möllendorff et al. IFMIF activation experiment on SS-316 steel as

benchmark

FISPACT-calculations using G-IEAF-2001/FP-256 data

Testing and Validation (2)



Nuclide Decay time, h

Activity, Bq/ kg (ALARA-calc.)

ALARA/ Experiment

FISPACT/ ALARA

Sc-46 49.68 1.0199E+05 1.91 1.002 Sc-48 49.68 2.2868E+06 1.46 1.001 V-48 49.68 2.9916E+06 2.77 1.000 Cr-48 49.68 4.8320E+05 4.60 1.000 Cr-49 1.66 1.9296E+08 0.87 0.999 Cr-51 49.68 2.9580E+08 1.06 1.000 Mn-52 49.68 2.7105E+07 3.51 0.984 Mn-54 49.68 1.8375E+07 1.06 0.993 Mn-56 25.93 4.1844E+07 1.09 1.002 Fe-52 25.93 5.0635E+05 1.48 0.985 Fe-59 49.68 3.7147E+05 1.17 1.001 Co-55 49.68 1.5870E+06 2.70 1.001 Co-56 49.68 8.2991E+06 2.94 1.001 Co-57 49.68 2.0675E+07 1.02 1.001 Co-58 49.68 8.3836E+07 1.14 1.001 Co-60 49.68 2.5289E+05 1.08 1.000 Co-61 1.66 2.3424E+08 2.25 1.000

SS-316 IFMIF activation benchmark

FISPACT/G-IEAF-2001/PY vs. ALARA/IEAF-2001/XS



Nuclide Decay time, h

Activity, Bq/ kg (ALARA-calc.)

ALARA/ Experiment

FISPACT/ ALARA

Ni-56 49.68 1.9961E+06 1.65 1.000 Ni-57 49.68 1.2975E+08 1.37 1.000 Y-87m 49.68 9.6815E+03 0.08 1.006 Y-87 49.68 8.5569E+04 0.48 1.003 Y-88 3600 1.0968E+04 1.04 1.007 Zr-86 49.68 3.4279E+03 0.03 1.000 Zr-88 700 2.3774E+04 1.04 1.004 Zr-97 49.68 1.3954E+05 0.03 1.000 Nb-90 25.93 3.4776E+06 0.46 1.003 Nb-92m 49.68 2.4108E+06 1.32 1.039 Nb-95 49.68 7.8172E+05 1.60 1.001 Nb-95m 49.68 1.1203E+06 1.19 1.001 Nb-96 49.68 4.2577E+06 1.87 1.000 Mo-90 49.68 2.4587E+04 1.70 1.001 Mo-93m 49.68 2.6532E+05 3.65 1.000 Mo-99 49.68 3.6165E+07 1.14 1.000 Tc-99m 49.68 3.4883E+07 1.14 1.000

SS-316 IFMIF activation benchmark

FISPACT/G-IEAF-2001/PY vs. ALARA/IEAF-2001/XS



• IEAF-2001: complete cross-section data library for activation and transmutation analyses (En 150 MeV, 1 Z 84) • Two different working libraries, G-IEAF-2001/XS-256 & G-IEAF-2001/PY for application calculations with different

approaches for inventory calculations (ALARA-, FISPACT-code)• Different approaches validated through series of benchmark calculations• Testing and qualification of IEAF- data performed for SS-316, V/V-alloy, Eurofer, W samples in IFMIF activation experiments• In routine use for applications to IFMIF neutron source• Available through NEA Data Bank & RSICC (ENDF data file & G-IEAF-2001/256-XS)

Summary



• Update, improvements & extension of IEAF-2001 ?– Benchmark results: need for improvements/revisions– En 20 MeV: Improved data (EAF-2003/JEFF-3.0 A)– Improved model codes / methodologies (e. g. GNASH, TALYS)– New experimental cross-section data– Extension to higher energies En > 150 MeV ? ( spallation)

• Strategy for updating:– Activation data library for neutron energies up to 1 GeV to include spallation transmutation productions – En > 150 MeV: Intranuclear cascade models– New evaluation in energy range 20 En 150 MeV (GNASH)– En 20 MeV: Use of JEFF-3.0

Outlook

review of ieaf-2001 cross section data libraries for ifmif activation and transmutation analyses

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