Development and Verification and Validation of MOC Module in Advanced Neutronics Lattice Code KYLIN-2

In order to simulate the complex fuel assembly in the advanced nuclear reactor, the method of characteristics（MOC） calculation module is developed in neutronics lattice code KYLIN-2. The MOC module adopts cyclic trajectory layout and angle quadrature set for special geometrical shapes, and uses ray prolongation method for other general geometrical shapes. The generalized coarse mesh finite differential（GCMFD） acceleration method is adopted in the MOC module. The numerical results show that the MOC module in KYLIN-2 code can calculate 2D neutronics problems accurately, and can be used in future reactor design.