IMPLEMENTATION AND APPLICATION OF THE CSG METHOD IN THE NECP-X CODE

Abstract

The CSG (Constructive Solid Geometry) method is widely used in the MC (Monte Carlo) codes because of its flexibility in geometry. In this paper, the CSG method is implemented in NECP-X, which is a newly developed high-fidelity neutronics code, to improve its geometric flexibility. To improve the user experience of using CSG, meshes for the multi-group transport calculation are automatically generated with only several parameters. Several problems are tested. The numerical results show that complicated reactor cores can be conveniently modeled and the results of NECP-X agreed well with those of the MC code.