The invention relates to the technical field of
neutron transport numerical calculation, in particular to a cross section generation method and device based on flux moment homogenization and transport correction
coupling and a storage medium, and the method comprises the steps: S1, building a geometric model of a reactor
assembly or lattice
cell, carrying out the energy Monte Carlo calculation, and generating a conventional cross section based on statistical data; s2, extracting a spherical
harmonic function flux moment and a total
reaction rate moment, calculating a total cross section spherical
harmonic function correction term, and introducing a conventional
scattering cross section to complete flux moment homogenization correction; and S3, exporting a first-order scattering matrix, carrying out transport correction to obtain a transport correction term, and correcting the conventional cross section according to the transport correction term and the total cross section spherical
harmonic function correction term to generate a final multi-group cross section. According to the method, the anisotropies of the total cross section and the
scattering cross section are synergistically corrected, the calculation precision of the method in the strong
anisotropy problem is improved on the premise of keeping the standard cross section
data structure, and the compatibility with a widely applied reactor core calculation program is ensured.