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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 the core contains a large amount of plutonium fuel, which undergoes more cycles and consumes more fuel, the neutron characteristics of the core will change. In order to verify the current computational accuracy of nuclear databases and existing procedures for this situation, the OECD / NEA presented the VENUS-2 benchmark experiment. The Cos MC program is a Monte Carlo program specifically designed for reactor calculations that can handle complex geometric models. In this paper, the VENUS-2 benchmark was calculated by using the latest nuclear database and Cos MC program. The calculation results are compared with other programs. The results show that the calculation results of Cos MC are in good agreement with the experimental measurements and some results calculated by other programs , Which shows that it is feasible to calculate the critical problem of COX-containing fuel core by using Cos MC program.