| 摘要 |
PROBLEM TO BE SOLVED: To provide a core analysis program capable of reducing an error accompanied by discretization, and shortening a calculation time of a neutron flux. SOLUTION: This core analysis program capable of analyzing a neutron flux in a core by solving a neutron transportation equation based on the method of characteristics includes: a ray tracing step for generating a plurality of neutron paths on an analysis object domain divided into a plurality of detailed domains; and a neutron flux calculation step for solving the neutron transportation equation based on the method of characteristics, and calculating the neutron flux in each detailed domain, relative to each neutron path generated in the ray tracing step. In the neutron flux calculation step, when a volume of each detailed domain calculated based on the neutron path is widely different from a volume of each detailed domain determined analytically beforehand, the neutron flux in each detailed domain is calculated by assuming that an incidence neutron flux entering each detailed domain is equal to a discharge neutron flux to be discharged from each detailed domain. COPYRIGHT: (C)2010,JPO&INPIT |
