蒙特卡罗粒子输运计算网格计数方法研究

摘要

Mesh tally method can accurately count the distribution of various physical quantities in reactor numerical simulation. The mesh tally of static parameters of rectangular coordinate system and cylindrical coordinate system was studied,which based on Super Monte Carlo Simulation Program for Nuclear and Radiation Process SuperMC. The TCA criticality facility of Japan Atomic Energy Research Institute was carried out for validation. The feasibility and the correctness of the method were demonstrated by the match of calculation results of SuperMC and MCNP.%在进行反应堆数值模拟时，通过网格计数方法可以精细地统计整个堆芯中多种物理量的空间分布情况。本文基于超级蒙特卡罗核计算仿真软件系统 SuperMC 发展了一种反应堆静态物理参数的网格计数方法。通过日本原子能研究所临界实验装置 TCA 例题进行了数值验证，计算结果与 MCNP 计算结果吻合较好，表明了本文方法的可行性与正确性。