Abstract
TRITON/GenPMAXS/PARCS sequence is a set of programs which is composed of lattice calculation code and core simulator. TRITON provides cross section datas by lattice calculations. GenPMAXS is an interface program between lattice physics codes and the core simulator. PARCS is a 3-D reactor core simulator which solves the steady-state, transient and multi-group neutron diffusion and SP3 transport equations. First, this TGP sequence simulates a simple PWR core and gets the results. The results will compare with the reference which is calculated by full-core transport calculation. This study aims to increase the use of experience and explore the advantages and limitations of this TGP sequence and provides the information of developing a local nodal core simulator. The results show that the keff, fuel assembly relative power and pin power distribution agree with the reference for the case of pure UOX core. The error of keff is about 18pcm. During the calculation, the study also discover that the values of absorption and scattering cross sections in PMAXS file are different from TRITON output and the results also show the importantance that the configurations of TRITON model and the setting of boundary conditions for generating cross section datas will have the huge impact on the results. However, the results for the case of mixed MOX core don’t present such well as the case of pure UOX core. Therefore, based on the paper review, this study introduces an supercell TRITON model to improve the cross section datas used in the core calculation. Although the results become better, there is a dilemma of the selection of power form functions. The study continues simulating this case with the multi-group, pin-wise calculation. Unfortunately, due to the runtime error, the results can not be produced. And the results of multi-group calculation test still have some problems so that further investigations are ongoing to clarify the cruxes of the problem.