Evaluation of nuclear reactor physics problems by combining deterministic and Monte Carlo methods

Service description

The solution of the slow neutron transport equation using the hybrid deterministic / Monte Carlo method. Calculations of reactivity, power profiles, nuclide composition of spent nuclear fuel, calculations of nuclear reaction types, taking into account the characteristics of the cells. Criticality Search. Neutron Spectrum and Flow Analysis.

Application

Analysis and evaluation of nuclear reactor physics problems.

Division

Laboratory of Nuclear Installation Safety (17)

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