基于VENUS-2临界基准的CosMC程序验证

Verification of CosMC Based on VENUS-2 Critical Benchmark

堆芯中含有大量经过多个循环、燃耗较高的钚燃料时,堆芯中子学特性会发生变化。为了验证目前核数据库及现有程序对这种情况的计算精度,经济合作与发展组织核能机构(OECD/NEA)提出了VENUS-2基准实验。Cos MC程序是专门用来进行反应堆计算的蒙特卡罗程序,可以处理复杂几何模型。本文采用最新核数据库及Cos MC程序对VENUS-2基准进行了计算,计算结果与其他程序做了对比,结果表明:Cos MC的计算结果与实验测量值以及其他程序计算的部分结果符合的较好,说明用Cos MC程序计算含混合氧化物(MOX)燃料堆芯的临界问题是可行的。

When a reactor core contains a large number of multiple cycles and higher burnup plutonium fuel, the core neutronics characteristics will change. To verify the accuracy of current database and existing nuclear software, OECD / NEA proposed VENUS-2 benchmark experiments. Cos MC is designed to perform the Monte Carlo reactor calculation that can handle the complex geometry. In this paper, the latest database and Cos MC is adopted to calculate VENUS-2 benchmark, and the results were compared with other software. The results show that: the calculation results of Cos MC agree well with the experimental results and the measured values. It is demonstrated that it is feasible for Cos MC to calculate the critical problem of the reactor core containing MOX fuel.