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European Activation System (EASY): Modeling and Transmutation in Fusion Research

This article discusses the European Activation System (EASY) and its application in fusion research, including modeling and transmutation processes. It covers the history, nuclear data, verification and validation, and future steps of EASY.

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European Activation System (EASY): Modeling and Transmutation in Fusion Research

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  1. Modern a, g, d, p, n-Induced Activation Transmutation SystemsEURATOM/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 CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority

  2. Outline • History - introduction • European Activation System • Activation – transmutation modeling • Nuclear data • Verification and Validation - V&V • Next steps and Conclusions

  3. 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

  4. 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

  5. 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 !!

  6. Theory • Set of differential equation to be solved • Si term for actinides and/or high energy Depletion Source σf for fission xs + fission yield σa for mt=5, total xs + activation yield

  7. MT Values • Grid of reactions including all 36 MT numbers defined in ENDF • and some of the now 86 defined in EAF-2010 n in  Z always decreases p,d,a in  Z may increases

  8. Experimental results • The results of the experiment are shown as Tables • These include: • C/E measured for the radionuclides • Experimental uncertainty (d) • Pathways (and % contribution) as calculated by FISPACT • Calculated uncertainty (D)

  9. Effective cross section Spectrum X Cross section sC

  10. Store data in SAFEPAQ-II sE = sC/ (C/E)activity Reference Experimental uncertainty Neutron spectrum

  11. 89Y(n,2n)88Y - integral Ignore? New data

  12. 89Y(n,2n)88Y - differential Region probed by rez_DF Remains validated

  13. 470 reactions in report 97 summed reactions 373 to individual states or not split 217 validated with score 6 156 discrepant with score 5 43 validated with score (6) 54 discrepant with score (5) 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

  14. European Activation File: n-induced • 2,233 nuclides • Stables and isomeric states (T½ > 1s) • 816 targets (H-1 to Fm-257) • 86 reaction types Cross sections Decay data Validation: C/E Validation: SACS

  15. Neutron-induced reactions • EAF handles 86 reaction types • Reactions that tend to be most important for all applications are: • (n,2n), (n,3n), (n,xn) multiplication • (n,p), (n,t), (n,a), (n,d), (n,h) Gas production • (n,g) – capture • (n,n'), (n,n) inelastic, elastic • (n,f) - fission • However, other reactions types can be as important for particular responses

  16. 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 a, g, 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

  17. 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: • Fusion studies • Reactor physics, fuel and waste management • Accelerators shielding, operational dose • GEN IV energy production systems • Medical application • Ores exploration • …..

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