Minor Actinides Cross-Sections
Integral Experiments at BFS Critical Facilities for Justification of Minor Actinides Transmutation and Their Analysis
Tech Area / Field
- FIR-EXP/Experiments/Fission Reactors
- FIR-ISO/Isotopes/Fission Reactors
- FIR-NOT/Nuclear and Other Technical Data/Fission Reactors
3 Approved without Funding
FEI (IPPE), Russia, Kaluga reg., Obninsk
- Research Coordination Center on the Problem of Muon Catalyzed Fusion and Exotic Quantum Systems, Russia, Moscow
- JAERI / Tokai Research Establishment / Center for Proton Accelerator Facilities, Japan, Tokai Mura\nEURATOM-Ciemat, Spain, Madrid\nTokyo Institute of Technology / Research Laboratory for Nuclear Reactors, Japan, Tokyo\nCEA / DCC / CEN Cadarache, France, Cadarache
Project summaryThe main goal of the project is the measurement of integral reactor parameters in critical experiments at BFS facilities and subsequent evaluation of minor actinide nuclear data on this basis. These data are indispensable for justifying of MA cross-sections in the conditions where neutron spectrum is formed by Pb(Bi) or by materials from typical molten-salt critical and subcritical systems to a great extent.
The following scientific and technical problems will be solved in the project:
– Fast critical assemblies with a large content of Pb(Bi) as well as materials typical for molten-salt systems will be assembled and studied;
– Integral fission cross - section will be measured for isotopes 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 241Am, 243Am, 244Cm, 245Cm as ratios to 235U cross section using fission chambers, activation and solid track detectors;
– Integral capture cross-sections will be measured for isotopes 237Np and 240 Pu;
– Central reactivity coefficients will be measured for isotopes 237Np, 239Pu, 240Pu, 241Pu, 241Am using the sample oscillation method;
– Doppler-effect for isotopes 238U, 237Np, 241Am will be measured by using the sample oscillation method with hot and cold samples in the core center;
– Uncertainties of the experimental results taking into account the methodical, geometrical and material uncertainties will be estimated;
– Numerical analysis of the measured values and their sensitivity to the MA nuclear characteristics will be implemented;
– Requirements to the accuracy of the major MA nuclear constants will be formulated to provide a necessary precision in the numerical simulation of MA effective burning systems;
– The results of benchmark experiments will be used for development and improving the numerical codes used for MA effective burning systems;
– The models of different MA effective burning systems will be developed and their numerical simulation will be performed using the improved codes and experimental data obtained;
– Evaluation of the obtained nuclear data will be done using the obtained results, the existing experimental data on MA irradiation in fast sodium reactor BN-350 as well as measurements of microscopic neutron cross-sections;
– The final product is the file of the evaluated MA nuclear data based on the performed experiments.
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