Method and system for solving multi-group neutron diffusion equation of reactor core of nuclear reactor

• Main Authors: LI TIANJUN, WANG ZHU, WANG XIANGLONG, WANG YUE, DU XIANGPENG, WAN TIANYUAN
• Format: Patent
• Language: Chinese; English
• Published: 23.06.2023
• Subjects: CALCULATING; COMPUTING; COUNTING; ELECTRIC DIGITAL DATA PROCESSING; INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTEDFOR SPECIFIC APPLICATION FIELDS; PHYSICS

The invention provides a method and system for solving a nuclear reactor core multi-group neutron diffusion equation, and relates to the technical field of nuclear reactor core calculation. The method comprises the following steps: reconstructing a nuclear reactor multi-group neutron diffusion equation into an elliptic partial differential equation, determining a coefficient matrix of the equation according to boundary conditions of the nuclear reactor multi-group neutron diffusion equation, and performing grid division on an established geometric model of a nuclear reactor core by using an unstructured grid so as to construct a core grid model; accurate simulation of the transient process of the reactor core neutrons in any geometrical shape is realized; a calculation method for establishing a multi-group diffusion equation based on the coefficient matrix and the reactor core grid model and a calculation method for calculating multi-group neutron macroscopic section parameters of the nuclear reactor and subs