1. Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3) Consistent data evaluations for tungsten isotopes including covariances P.Pereslavtsev, A. Konobeyev, U. Fischer Association FZK-Euratom, Forschungszentrum Karlsruhe, Germany

2. FENDL-3, IAEA Outline  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

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

4. FENDL-3, IAEA Nuclear data evaluation Covariances and uncertancies Data processingNuclear data validationConsistent evaluation Microscopic cross sections Corrections based on Monte-Carlo method Strict ENDF-6 format Benchmark MCNP calculations Consistent nuclear data evaluation Data file for users

5. FENDL-3, IAEA 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. FENDL-3, IAEA Optical model calculations  Global OMPs for n, p, d, t, 3 He,  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 New tungsten evaluations

7. FENDL-3, IAEA Resonance parameters Resonance parameters are taken from existing evaluations and checked against recommended data (S.Mughabghab, 2006) Isotope Resolved region Unresolved region 182 W JENDL-3.3ENDF/B-VII 183 W ENDF/B-VII 184 W ENDF/B-VII 186 W ENDF/B-VII Evaluated resolved resonance parameters used are very close to the data by S. Mughabghab

8. FENDL-3, IAEA 182 W cross sections evaluations (examples) EAF-2007

9. FENDL-3, IAEA 183 W cross sections evaluations (examples)

10. FENDL-3, IAEA 184 W cross sections evaluations (examples)

11. FENDL-3, IAEA 186 W cross sections evaluations (examples) EAF-2007

12. FENDL-3, IAEA Elastic scattering angular distributions

13. FENDL-3, IAEA Elastic scattering angular distributions (questions...)

14. FENDL-3, IAEA Elastic scattering angular distributions (high energies)

15. FENDL-3, IAEA Inelastic scattering angular distributions

16. FENDL-3, IAEA Neutron emission spectra (low energy)

17. FENDL-3, IAEA Neutron emission spectra (high energy)

18. FENDL-3, IAEA IFMIF related data

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

20. FENDL-3, IAEA  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 Evaluation of covariances using Monte Carlo approach

21. FENDL-3, IAEA Evaluation of cross-sections and covariances using nuclear models Set of “best” model parameters p 0 ={p 01,….p 0M } Result of the calculation s 0 ={s 01,..... s 0N } Choice of parameters by Monte Carlo p k ={p 01  D p k1,,..…,p 0M  D p kM } Covariance matrix after K histories for i,j=1,N (energy) Evaluated cross-section

22. FENDL-3, IAEA Calculations of uncertainties Uncertainty before and after the use of experimental data

23. FENDL-3, IAEA Continuous uncertainty evaluation Evaluated uncertancies for 183 W

24. FENDL-3, IAEA Calculations of corelation matrix After nuclear model calculations Final results including experimental data

25. FENDL-3, IAEA Calculations of corelation matrix After nuclear model calculations Final results including experimental data

26. FENDL-3, IAEA Accounting for experimental data uncertanties Final evaluation

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

28. FENDL-3, IAEA Data files processing  ENDF-6 format control with standard CHECKERs  NJOY99.245 processing done for both evaluations (covariances were not considered) FileIAEAFZK MF3FIZCON complains☺ MF10FIZCON error☺ MF14FIZCON error☺ MF32CHECKR error- MF33FIZCON errorFIZCON complains MF34--

29. FENDL-3, IAEA neutrons Tungsten blocks 5 cm 10 cm 15 cm 35 cm FNG tungsten experiment

30. FENDL-3, IAEA Results for neutron spectra

31. FENDL-3, IAEA Results for photon spectra

32. FENDL-3, IAEA C/E flux integrals

33. FENDL-3, IAEA MCNP benchmark calculations (reaction rates)

34. FENDL-3, IAEA 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