The present invention provides a method for accelerating
neutron transport calculation of a three-dimensional characteristic line of a domestic DCU architecture, and belongs to the field of high-
performance computing technology. The method includes: constructing uniform / non-uniform coarse-mesh finite difference grid
geometric modeling according to the reactor
geometric modeling and domain
decomposition structure; in the trajectory generation and
trajectory segmentation stage, recording the relationship between the flat
source area and the coarse-
mesh grid and the coarse-
mesh grid and the communication domain, storing the trajectory segments reaching the vertices, edges and faces of the coarse-
mesh grid, storing the trajectory segments located at the domain boundary, recording the trajectory connection sequence between adjacent communication domains, and the coarse-mesh grid surface adjacency relationship; in the transport scanning stage, according to the domain
decomposition structure, sending the calculation task to the device end, storing the
neutron flow on the surface of the coarse-mesh grid to which the trajectory segment belongs according to the coarse-mesh grid points, edges and faces to which the trajectory segment belongs, and storing the
neutron flow at the communication domain boundary that needs
information transmission; transmitting the transport solution calculation result to the coarse-mesh finite difference solution module, constructing a coarse-mesh finite difference equation group and solving it using the successive super-relaxation iteration method, updating the flux of each flat
source area according to the calculation result and calculating the effective
neutron multiplication factor in the current iteration.