Nuclear Data Evaluation Activities in KAERI

1. Nuclear Data Evaluation Activities in KAERI Hyeong Il Kim* Nuclear Data Evaluation Lab.,Korea Atomic Energy Research Institute *E-mail: hikim@kaeri.re.kr

2. Table of Contents • Introduction • Evaluation Procedure • Extension of EMPIRE-II • ECISPLOT • Benchmark tests for FENDL-2.1 • Recent Evaluation Results • Neutron induced reactions (W) • Charged particle induced reactions (Al) • Summary and Further Works

3. Introduction • Nuclear Data Evaluation Lab. (NDEL) • Staffs (8+1) • Evaluation (4), Processing & Benchmark (4), and Secretary (1) • Recent achievements • Evaluation (contributed to ENDF/B-VII.0) • 32 FPs collaborated with BNL • 124 Photonuclear Evaluations ( IAEA-CRP) • Processing (contributed to NEA/DB) • MATXS-format 150-group neutron libraries for fast reactors:KAFAX-E70 (ENDF/B-VII.0), KAFAX-F31 (JEFF-3.1), and KAFAX-J33 (JENDL-3.3), • Benchmark • Integral tests for ENDF/B-VII.0, JEFF-3.1, JENDL-3.3 and so on. • Al, Fe, Ni, Si, and W (FENDL-2.1)

4. Cont’d • Recent Activities related with FENDL Library • Motivated by our benchmark results for FENDL-2.1 • Oktavian (Al, Si, Ni, Fe, W) • FNS, Criticality benchmark (W) • New 182,183,184,186W evaluations up to 20 MeV (EMPIRE-II) • Individual channels were in good agreements with measurements. • Integral measurements are reproduced well. • They are being extended to 150 MeV including the covariance files. • d- and p- induced reactions for 27Al (Talys) • In addition, doing the evaluations for n-, d-, and p- induced reactions on Si, Ni and Fe

5. Evaluation Procedure

6. Evaluation, Processing and Benchmark • Nuclear Reaction codes • EMPIRE-II (Neutron), TALYS (Charged Particles) • Initial Input data taken from RIPL-II ( next RIPL-III) • OMP optimized by ECISPLOT • Nuclear models by comparison with measurements • Evaluation • Check Not only individual channels but also the Integral tests • Almost no manual works to produce the ENDF-6 formatted files except the complaints by checking codes from time to time • Extension of EMPIRE to resonance module in collaboration with BNL • Processing (Njoy-99.161) • Benchmark (MCNPX-2.5.0)

7. EMPIRE-II Resonance module with Covariance The resonance module: • Reads data from the electronic version of the Atlas • Makes statistically justified guesses for unknown parameters • Uses average resonance properties to construct unresolved resonance region • Allows manual adjustment of parameters, their uncertainties, energy ranges, average quantities • Creates ENDF-6 files MF = 2 and MF = 32 Determination of covariances: • Uncertainties compiled in the Atlas used as a basis • Missing uncertainties are estimated • Correlations between resonance parameters can be introduced • Ensuring consistency between uncertainties assigned to parameters for the first few resonances and experimental uncertainties for the thermal cross sections

8. Extension of EMPIRE-II (cont’d ) • Graphical User Interface (GUI)

9. Extension of EMPIRE-II (cont’d ) Graphical analysis of resonance energies - helps to determine the upper boundary of the resolved resonance region. Plot of the Porter-Thomas distribution - helps to determine the average resonance parameters such as a level spacing and neutron strength functions for s- and p-waves. Comparison of cross sections with experimental data and ENDF/B-VII.0 for Total cross sections

10. ECISPLOT • Fitting or searching OMP parameters using the results of ECIS cal. • Automatic Fit: Simulated Annealing (SA) • Manual Fit • Reads C4 formatted files for experimental data • Reads and writes the RIPL-2 format for OMP • Directly used as inputs of EMPIRE and TALYS • Being still developed • Fast for spherical OMP but slow for CC OMP • Going to Parallel computing • Available new formula

12. Benchmark tests for FENDL-2.1 < Distribution of materials by original source of evaluation in FENDL-2.1 > • Oktavian • Pulsed sphere experiments for neutron and gamma-ray leakage spectra at the D-T neutron source facility of Osaka University • Benchmarks for Ni, Fe, Al, Si, and W spheres taken from SINBAD

13. Gamma leakage spectrum (Al)

14. Gamma leakage spectrum (Si)

15. Neutron leakage spectrum (Ni)

16. Neutron leakage spectrum (W)

17. Tungsten Evaluation

18. Capture cross sections

19. (n,2n) cross sections

20. Neutron Production

21. Oktavian

22. FNS

23. Criticality Benchmark

24. Charged particle induced reactions • d-, p- and a- induced reactions • TALYS-0.72 (=>TALYS-1.0) • Incident energy: up to 150 MeV • Modified OMP

25. Proton Induced Reactions

26. Production cross sections induced by proton

27. Residual Cross Sections induced by Proton

28. Deuteron Induced Reactions

29. Alpha induced reactions

30. Summary and Further works • Summary • Evaluation based on EMPIRE-II, TALYS, ECISPLOT codes • Performed Benchmark tests for 5 materials in the FENDL-2.1 library. • Completed evaluations on four tungsten isotopes up to 20 MeV and extending 150 MeV including covariance files. • Calculated p-, d-, and a- induced reactions for 27Al. • Further works • Short term: Evaluations for n-, d-, p- induced reactions on Al, Si, Ni, and Fe • Long Term: Pre-emptive improvement of nuclear data for future nuclear R&D applications