ccfe is the fusion research arm of the united kingdom atomic energy authority modern , d, p,...

CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority

Modern , d, p, n-Induced Activation Transmutation

Systems EURATOM/CCFE Fusion Association

J-Ch. Sublet and L. Packer (CCFE)Culham Centre for Fusion Research, Abingdon, United Kingdom

J Kopecky (JUKO)Juko research, Kalmanstraat 4, 1817 HX Alkmarr, The Netherlands

D. Rochman, A.J. Koning (NRG) Nuclear research and Consultancy Group, Petten, The Netherlands

Outline• History - introduction

• European Activation System

• Activation – transmutation modeling

• Nuclear data

• Verification and Validation - V&V

• Next steps and Conclusions

EASY

• European Activation System (EASY) consists of:

– European Activation File (EAF) nuclear data libraries– FISPACT inventory code– EASY User Interface– SAFEPAQ-II library production application– Documentations

– Validation and Verifications, V&V reports since the 90’s

EAF - Nuclear data libraries

• European Activation File (EAF) is a set of nuclear data libraries– Neutron-induced cross sections (up to 60 MeV)– Uncertainty data– Decay data– Fission yields– Biological hazards– Clearance data– Charged particle data (for SCPR, A (n,p) B )– Deuteron-induced cross sections – Proton-induced cross sections

EAF-2010 released in April 2010

FISPACT-2010– Inventory code – calculates the build up, transmutation of

nuclides following particles exposure– Developed over the last 30 years for fusion applications– Developed from the UK fission power reactor code FISPIN– Features

• External libraries of cross section and decay data• 100 elements, from hydrogen to fermium handled• Arbitrary irradiations (multiple pulses)• Arbitrary neutron spectrum up to 60 MeV• Gas production and isomers• Sensitivity and uncertainty calculations• Dominant nuclides and pathways• Fissionable actinides• Sequential charged particle reactions

Unique !!

Theory

ikk

akkik

k

fkki

iij

ijijjiiii

YNYNS

SNNdtdN

)()(

• Set of differential equation to be solved • Si term for actinides and/or high energy

Depletion

Sourceσf for fission xs + fission yieldσa for mt=5, total xs + activation yield

MT Values

N-7 N-6 N-5 N-4 N-3 N-2 N-1 N N+1

Z (n,8n) 161

(n,7n) 160

(n,6n) 153

(n,5n) 152

(n,4n) 37

(n,3n) 17

(n,2n) 16

(n,n’) 4

(n,) 102

Z-1 (n,2nt) 154

(n,nt), (n,2np) 33,42

(n,t), (n,nd) 105,32,41

(n,d), (n,np) 104, 28

(n,p) 103

Z-2 (n,6na) 167

(n,4na) 165

(n,3na) 25, 200

(n,2na) 24

(n,n’a) 22

(n,a), (n,nh) 107,34,116

(n,h), (n,pd) 106,44,115

(n,2p) 111

Z-3 (n,2npa) 159

(n,da),(n,npa) 117,45

(n,pa) 112

(n,3p) 197

Z-4 (n,2n2a) 30

(n,n2a) 29

(n,2a) 108

Z-5 (n,nt2a) 36

(n,t2a) 113,35

(n,d2a) 114

Z-6 (n,n3a) 23

(n,3a) 109

Classical MT’s New MT’s

- Grid of reactions including all 36 MT numbers defined in ENDFand some of the now 86 defined in EAF-2010

n in Z always decreasesp,d, in Z may increases

Experimental results– The results of the experiment are shown as Tables– These include:

• C/E measured for the radionuclides• Experimental uncertainty ()• Pathways (and % contribution) as calculated by FISPACT• Calculated uncertainty ()

Effective cross sectionfng eurofer.asc

Neu

trons

per

leth

argy

inte

rval

Neutron Energy (eV)

1.0E+10

1.0E+01

1.0E+02

1.0E+03

1.0E+04

1.0E+05

1.0E+06

1.0E+07

1.0E+08

1.0E+09

1E-04 1E-03 1E-02 1E-01 1E+00 1E+01 1E+02 1E+03 1E+04 1E+05 1E+06 1E+07

Fe-56(n,2n)Fe-55

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

1.5E-01

3.0E-01

4.5E-01

6.0E-01

7.5E-01

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07Experimental data

Spectrum X Cross section

C

ii

iii

Store data in SAFEPAQ-II

E = C / (C/E)activity

Neutron spectrum Reference Experimental uncertainty

89Y(n,2n)88Y - integralIntegral C/E for Y-89(n,2n)Y-88C

/E

Neutron Spectrum

C/E = 0.8621

C/E = 1.1112

C/E = 1.0259

C/E = 1.1378

C/E = 1.4887

1.10

0.91

0.80

1.00

1.20

1.40

1.60

fns_7hour fns_5min fng_Y tud_Y rez_DF

New data

Ignore?

Y-89(n,2n)Y-88

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

3.0E-01

6.0E-01

9.0E-01

1.2E+00

1.5E+00

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmPAT79RI 99KGU00LAS75KYU79MOH84ANL87BRC81LAS75KOS81FEI89FEI89SAV98BRC02RI 99LAS75AUB76JAE93LAS77AEP89

89Y(n,2n)88Y - differential

Region probed by rez_DF

Remains validated

Summary– Large database of integral data– EASY approach, C/E for nuclide → C/E for reaction– Use integral + differential data → Quality score– Results for EASY-2007

470 reactions in report

373 to individual states or not split

97 summed reactions

217 validated with score 6

43 validated with score (6)

54 discrepant with score (5)

156 discrepant with score 5

European Activation File: n-induced

(n,p) for Final

Max

cro

ss s

ectio

n (b

)

Asymmetry (s)

1E-03

1E+01

1E-02

1E-01

1E+00

0.00 0.05 0.10 0.15 0.20 0.25

Integral C/E for Fe-54(n,p)Mn-54

C/E

Neutron Spectrum

C/E = 0.9504

C/E = 1.0436

C/E = 0.9722

C/E = 1.0833

C/E = 0.9669C/E = 0.9422

C/E = 1.0302

C/E = 0.9926C/E = 0.9949

C/E = 1.1032C/E = 1.1150

C/E = 1.1645

C/E = 0.9806

C/E = 1.0208

C/E = 1.0569

C/E = 1.2776

1.10

0.91

0.70

0.90

1.10

1.30

1.50

sneg_2 fng_f82h.asc cf252_flux_1 cf252_flux_1 cf252_flux_1 fzk_ss316 fng_vanad.asc rez_DFsneg_1 fzk_2 fns_7hour cf252_flux_1 cf252_flux_1 fzk_ss316 fzk_1 fng_eurofer.asc

Y-89(n,2n)Y-88

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

3.0E-01

6.0E-01

9.0E-01

1.2E+00

1.5E+00

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmPAT79RI 99KGU00LAS75KYU79MOH84ANL87BRC81LAS75KOS81FEI89FEI89SAV98BRC02RI 99LAS75AUB76JAE93LAS77AEP89

Validation: SACS Validation: C/E

Cross sections

•816 targets (H-1 to Fm-257)•86 reaction types

•2,233 nuclides•Stables and isomeric states (T½ > 1s)

Decay data

EAF-2010

5096 important reactions

2265 major reactions

1728 reactions with any experimental data

66256 neutron induced reactions

470 reactions with integral data

•Reactions that tend to be most important for all applications are:

– (n,2n), (n,3n), (n,xn) multiplication

– (n,p), (n,t), (n,), (n,d), (n,h) Gas production

– (n,) – capture– (n,n'), (n,n) inelastic, elastic– (n,f) - fission

•However, other reactions types can be as important for particular responses

Neutron-induced reactionsEAF handles 86 reaction types

New features

• The FISPACT code is been re-written in modern Fortran-95 language and structure – already at phase 3

• Better, more user friendly multi-platforms, pre and post processing GUI tools are developed

• The , d, p, n-induced data libraries energy ranges are extended to 200 MeV

• Alpha and gamma induced reactions added• Universal 616 energy groups structure• Temperatures dependant n-cross section libraries• Probability table derived self-shielding factors in the

resonance resolved and unresolved energy range

Conclusions

• The now a day performance of computer cluster and the development of modern computing techniques allow building a new generation of truly multi purpose activation transmutation systems to be used in:

1. Fusion studies2. Reactor physics, fuel and waste management 3. Accelerators shielding, operational dose4. GEN IV energy production systems5. Medical application6. Ores exploration7. …..