Neutron flux calculation of reactor pressure vessel for MOX fuel core

The reactor pressure vessel (RPV) neutron flux calculation method for MOX fuel core was preliminarily researched, especially the core source calculation method for MOX fuel core. Based on three-dimensional discrete ordinate code TORT, the RPV fast neutron flux was calculated for CAP1400 reaction core carrying 50% MOX fuel, and the difference between MOX fuel core and UO2 fuel core was compared and analyzed. The results demonstrate that CAP1400 reaction core carrying 50% MOX fuel can satisfy the request of the radiation safety of RPV. For radiation shielding optimization, the suggestion is that much attention should be paid to the core loading pattern selection for the pivotal position.