JMCT程序临界安全基准校验计算与分析

摘要

JMCT程序是北京计算数学与应用物理研究所自主开发的蒙特卡罗方法粒子输运计算程序。从国际临界安全实验数据库中选取棒栅类、U 系、Pu系、233 U 系实验方案对JMCT程序进行验证,验证涵盖了常见裂变元素(如 U,Pu等)从低富集度到高富集度的快、热能区,同时也包含了常见的中子毒物以及反射层材料。将JMCT程序的计算结果与基准实验值进行对比,并且与 MCNP,MONK 程序的计算结果进行了比较。结果表明,在检验的范围内,JMCT程序具有与国际通用蒙特卡罗方法粒子输运程序一样良好的计算精度。%JMCT developed by Institute of Applied Physics and Computational Mathematics is a transport code based on Monte Carlo method.A series of benchmark experiments picked up from the international nuclear critical experiment database, were used to validate JMCT.The validation includes common fission nuclides(such as U and Pu),from lower enrichment to high-er enrichment,their thermal neutron groups and fast neutron groups,and common neutron poison and reflector.The results of JMCT were compared with the results of experiments by MCNP and MONK.The correctness of JMCT is preliminarily verified.