CORE DESIGN METHOD, DEVICE AND PROGRAM USING CONTINUOUS ENERGY MONTE CARLO METHOD

摘要

PPROBLEM TO BE SOLVED: To accurately calculate an adjoint angle neutron flux using a continuous energy Monte Carlo method. PSOLUTION: This core design method includes a step (S4) of setting a plurality of neutron sources for evaluating a nuclear reactor output, a step (S5 and S6) of calculating the number of generated fission neutrons for each generation by calculating the transportation of neutrons by the continuous energy Monte Carlo method for each neutron source for each generation over the preset number of generations, a step (S7) of calculating the ratio in the number of generated fission neutrons between the generations by dividing the numbers of generated fission neutrons for respective generations by each other, and a step (S8) of calculating the limit value of the nuclear reactor output originating in each neutron source set in the process of (S4) by multiplying the ratios in the number of generated fission neutrons between the generations by each other. PCOPYRIGHT: (C)2011,JPO&INPIT