Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)

1. Consistent data evaluations for tungsten isotopesincluding covariances P.Pereslavtsev, A. Konobeyev, U. Fischer Association FZK-Euratom, Forschungszentrum Karlsruhe, Germany Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)

2. FZK nuclear data evaluation work Consistence of nuclear data Quality of the evaluated data Tungsten nuclear data evaluations for energies up to 150 MeV Calculations of covariances for the evaluated cross sections Validation of the new general purpose neutron transport files TUD measurements on W at FNG FNG experiment on W Outline

3. Nuclear data evaluation Uncertainty evaluations Covariance matrix preparation Nuclear data validation (MCNP5) Nuclear data evaluation in FZK FZK

4. Nuclear data evaluation Data processing Nuclear data validation Consistent evaluation Covariances and uncertancies Consistent nuclear data evaluation Microscopic cross sections Corrections based on Monte-Carlo method Strict ENDF-6 format Benchmark MCNP calculations Data file for users

5. Assurance of evaluated data quality Quality of the microscopic cross sections GNASH and ECIS codes for nuclear model calculations Comparison with experimental data Comparison with available evaluations Correction of the data during covariances calculations Quality of the data representation (format) Use of the standard format checkers NJOY processing Cross check of the evaluated data Quality of the integral data Accurate MCNP transport calculations Evaluated data modifications

6. New tungsten evaluations • Optical model calculations • Global OMPs for n, p, d, t, 3He,  from 0.001 to 150 MeV • ECIS coupled-channel and DWBA calculations • Nuclear data evaluation • GNASH, ECIS • Experimental data • Systematics • Available evaluations • Covariance matrices calculations • Unified Monte Carlo approach (D. Smith) • Nuclear model calculations • Experimental data • Corrections of evaluated data

7. Resonance parameters Resonance parameters are taken from existing evaluations and checked against recommended data (S.Mughabghab, 2006) Evaluated resolved resonance parameters used are very close to the data by S. Mughabghab

8. EAF-2007 182W cross sections evaluations (examples)

9. 183W cross sections evaluations (examples)

10. 184W cross sections evaluations (examples)

11. EAF-2007 186W cross sections evaluations (examples)

12. Elastic scattering angular distributions

13. Elastic scattering angular distributions (questions ...)

14. Elastic scattering angular distributions (high energies)

15. Inelastic scattering angular distributions

16. Neutron emission spectra (low energy)

17. Neutron emission spectra (high energy)

18. IFMIF related data

19. Gas production data IAEA: p,  given in the files FZK: p, d, t, 3He,  given in the files

20. Evaluation of covariances using Monte Carlo approach • Selection and treatment of experimental data • Calculations using nuclear models. Evaluation of covariance matrix by Monte Carlo method (D. Smith) • Evaluation of data and covariances using experimental data and results of code calculations • Recording in ENDF/B format

21. Evaluation of cross-sections and covariances using nuclear models Result of the calculation s0={s01, ..... s0N} Set of “best” model parameters p0={p01,….p0M} Choice of parameters by Monte Carlo pk={p01 D pk1,,..…,p0M  D pkM} Covariance matrix after K histories for i,j=1,N (energy) Evaluated cross-section

22. Calculations of uncertainties Uncertainty before and after the use of experimental data

23. Continuous uncertainty evaluation Evaluated uncertancies for 183W

24. Calculations of corelation matrix After nuclear model calculations Final results including experimental data

25. Calculations of corelation matrix After nuclear model calculations Final results including experimental data

26. Final evaluation Accounting for experimental data uncertanties

27. MF=1 MF=2 MF=3 MF=33 MF=15 MF=12 MF=14 General description.MT=451 Resonance parameters. MT=151 MT=1, 2, 4, 5, 16, 17, 22, 24, 28, 41, 51-70, 91, 102,103, 104, 105, 106, 107 Angular distributions.MT=2, 51-70 MF=4 Energy-angular distributions. MT=16,22,28,91, 103-107 (below 20 MeV), MT=5 (above 20 MeV): particles, photons, recoils MF=6 Photon production multiplicities and transmission probabilities. MT=16,22,24,28,41, 51-70,91,102-107 Photon angular distributions. MT=16,22,24,28,41,51-70,91,102-107 Covariance matrices. MT=1, 2, 4, 5, 16,22,24,28, 91, 102-107 Photon energy spectra. MT=16,22,24,28,91,102-107 Evaluated files content

28. FNG tungsten experiment 35 cm 15 cm 10 cm 5 cm neutrons Tungsten blocks

29. Results for neutron spectra

30. Results for photon spectra

31. C/E flux integrals

32. MCNP benchmark calculations (reaction rates)

33. Conclusions • Consistent approach for nuclear data evaluations was elaborated in FZK • This method includes nuclear data evaluation up to 150 MeV, covariance matrixes calculations for all nuclear reactions presented in the files, nuclear data processing and finally benchmark calculations with MCNP • The microscopic evaluated data show good agreement with available experimental data • Calculated uncertainties are continuous in full energy range from thermal point to 150 MeV • Results of the benchmark calculations show good agreement with measured values • The developed approach is going to be applied for angular distributions covariance matrixes calculation