RESULTS OF IMPLEMENTATION OF NEW PROMPT FISSION NEUTRON SPECTRA DATA IN ROSFOND

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

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. • 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. 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) 3

4. Selected Test Models for the Analyses • HEU-Metal-Fastsystems • HEU-Sol-Thermalsystems • PU-Metal-Fastsystems • PU-Sol-Thermalsystems • 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

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 ABBNgroupdata set 299 n + 127 NJOY GRUCON ROSFOND Evaluated Nuclear Data Files FOND-2 CONSYST ENDF/B-6, 7 JENDL-3,4 JEFF-3, etc. Format GMF 299 n + 15  P5 PRECONS NJOY Reactor Physics codes TRIGEX FFCP Format ACE SUBGRAN (subgroups) DORT-TORT, KATRIN MCNP Continuous MCNP Group Mode MMKKENOGroup Mode Shielding Monte-Carlo codes

7. New 239PU PFNS

8. Table 1 – Description of finite plutonium Pruvost’s test models

9. Results in Pruvost’s Curve

10. Table 2 – Description of the PMF systems

11. Results for PMF Systems

12. Results for PMF Systems (comparison to experiment)

13. Results for PST Systems 13

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

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 lead coolant + 0,25%.

18. Thank you