Validation of the code package MCPV with continuous-energy data library

Abstract

The results of the validation of the code package MCPV for the calculation of radiation transport within VVER-1000 reactor type near-vessel space using a continuous-energy data library are presented. The validation is carried out based on the experimental data obtained in mock-up and full-scale experiments. It is shown that the code package MCPV can be used to simulate neutrons and gamma quanta transport through the complicated heterogeneous environment of a nuclear reactor and to obtain the valid values of the functionals of the neutron and gamma fluxes within VVER-1000 near-vessel space.

Keywords

• program of radiation transport calculation
• vver-1000
• mcpv.