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.

• 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.

List of experiments selected for the analyses and categorized in DICE database:

• 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.

HEU-Metal-Fast systems

• HEU-Metal-Fast systems

• HEU-Sol-Thermal systems

• PU-Metal-Fast 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

• 2 LMFR Test models

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.

• 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.

LMFR with sodium coolant -0,36%.

• LMFR with sodium coolant -0,36%.

• LMFR with lead coolant + 0,25%.