Abstract
In order to more accurately simulate the strong neutronics physical and thermal-hydraulic coupling phenomenon in a typical PWR, ARMcc (a software for the physical thermal coupling calculation of PWR core) is developed. In the ARMcc, the physical calculation module is based on the fourth-order nodal expansion method (NEM) and nodal Green’s function method (NGFM), the thermal-hydraulic calculation module is based on one-dimensional single-phase single channel heat transfer model and one-dimensional cylinder heat conduction calculation model, and the finite volume method (FVM) and finite difference method (FDM) are used to solve one-dimensional cylinder heat conduction model in the program. Based on the typical PWR benchmark NEACRP-L-335, the steady-state coupling calculation ability of the program is verified. The key parameters of the core calculated by the program, such as critical boron concentration and core Doppler temperature, are in good agreement with the reference results. The deviation between the critical boron concentration and the reference results is less than 5 ‰. In addition, the influence of four calculation modes on the simulation of core physical thermal coupling process is studied, and the results of PARCS program are selected as reference. It is found that NGFM + FDM calculation mode can more accurately simulate the core fuel Doppler temperature, core outlet coolant temperature and core power distribution; NEM + FVM can more accurately simulate the core fuel maximum temperature.
