1. RESULTS OF IMPLEMENTATION OF NEW PROMPT FISSION NEUTRON SPECTRA DATA IN ROSFOND Gennady Manturov, IPPE 2nd RCM Prompt Fission Neutron Spectra, 13-16 December 2011, Vienna, Austria

2. 2 Introduction The main goal of the work is to use critical experiments for investigation of influence and testing of PFNS data for 235U and 239Pu. The main goal of the work is to use critical experiments for investigation of influence and testing of PFNS data for 235U and 239Pu. International Handbook of Evaluated Criticality Safety Benchmark Experiments includes detailed descriptions of conditions and results of near 5000 critical experiments performed in many countries in the world. Hereafter a set of selected experimental configurations from ICSBEP Handbook is applied for investigation of the influence and testing of Prompt Fission Neutron Spectra for 235U and 239Pu.

3. 3 List of experiments selected for the analyses and categorized in DICE database: for uranium fuel: HEU-METAL-FAST and HEU-SOL-THERM type. for plutonium fuel: PU-METAL-FAST and PU-SOL-THERM type. For the most of experimental configurations input data files are constructed to perform calculations using Monte-Carlo codes MMKKENO and MCNP. Calculation results of the selected experimental configurations was obtained using MMKKENO and MCNP: with original ROSFOND nuclear data files, with modified ROSFOND nuclear data files, according to V.Maslov’s recommendations for new evaluation of the Prompt Fission Neutron Spectra for 235U and 239Pu isotopes. Introduction (cont’d)

4. 4 Selected Test Models for the Analyses HEU-Metal-Fast systems HEU-Metal-Fast systems HEU-Sol-Thermal systems HEU-Sol-Thermal systems PU-Metal-Fast systems PU-Metal-Fast systems PU-Sol-Thermal systems PU-Sol-Thermal systems So called Pruvost’s curve was selected as a test object. The curve reflects dependence of critical radius for the sphere, filled with solution of plutonium (or uranium) and surrounded by thick water- reflector, from concentration of plutonium (or uranium) in the solution. The minimal plutonium concentration corresponds to solution with k∞ equal to 1, the maximal – corresponds to metallic fuel So called Pruvost’s curve was selected as a test object. The curve reflects dependence of critical radius for the sphere, filled with solution of plutonium (or uranium) and surrounded by thick water- reflector, from concentration of plutonium (or uranium) in the solution. The minimal plutonium concentration corresponds to solution with k∞ equal to 1, the maximal – corresponds to metallic fuel 2 LMFR Test models 2 LMFR Test models

5. Hereafter we limit self by considering practical important cases – a set of experiments PU-SOL-THERM with plutonium aqueous solutions and PU-MET- FAST with metal plutonium.

6. Calculation Scheme Using Group and Continuous Nuclear Data CONSYST ABBN group data set 299 n + 127  Format GMF 299 n + 15  P 5 MMKKENO Group Mode TRIGEX FFCP MCNP Group Mode PRECONS Evaluated Nuclear Data Files FOND-2 NJOY GRUCON MCNP Continuous NJOY Format ACE ENDF/B-6, 7 JENDL-3,4 JEFF-3, etc. SUBGRAN (subgroups) ROSFOND Reactor Physics codes Monte-Carlo codes DORT-TORT, KATRIN Shielding

7. 7 New 239PU PFNS

8. Table 1 – Description of finite plutonium Pruvost’s test models № kg 239 Pu per liter H 2 O № № № № 10.00850.01290.03130.51710.0 20.00960.013100.05141.01814.0 30.01070.014110.1152.01919.74 40.01180.020120.2165.0

9. 9 Results in Pruvost’s Curve

10. Table 2 – Description of the PMF systems №ID % fissions in E>100 keV Reflector type №ID % fissions in E>100 keV Reflector type 1 PMF0198- 9 PMF1293Al 2 PMF2298- 10 PMF2491HCH2 3 PMF4098Cu 11 PMF44b90Fe 4 PMF2397C 12 PMF44a87BeBe 5 PMF1097U 13 PMF1179H2O 6 PMF2897SS 14 PMF37b75H2O 7 PMF1596Fe 15 PMF37f69H2O 8 PMF069595U 16 PMF1665H2O

11. 11 Results for PMF Systems

12. 12 Results for PMF Systems (comparison to experiment)

13. 13 Results for PST Systems

14. 14 Results for PST systems (comparison to experiment)

15. Results for HEU Systems (last year results)

16. Results for HST Systems (last year results)

17. Results in Keff for LMFR LMFR with sodium coolant -0,36%. LMFR with sodium coolant -0,36%. LMFR with lead coolant + 0,25%. LMFR with lead coolant + 0,25%. 17

18. 18 Thank you