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基于最新释放的ENDF/B-VII.1核评价库,采用核数据加工处理程序NJOY-99制作基于WIMS格式的多群数据库,针对轻水堆(Light Water Reactor,LWR)基本燃料栅元均匀化计算基准题,以235U、238U核素为主要分析对象,对比研究了NJOY程序输入模块参数的选择对截面库制作加工时间、积分量ΔKeff及灵敏度的影响,得到优化的输入参数选择方案。基准例题验证结果表明:所制作的多群数据库是正确的,Keff计算精度较高,可为压水堆燃料组件均匀化计算提供数据基础。
Based on the newly released ENDF / B-VII.1 nuclear evaluation database, a multi-group database based on the WIMS format was produced by using the nuclear data processing program NJOY-99. The basic fuel cell homogenization for Light Water Reactor (LWR) Computation of benchmark questions, 235U, 238U nuclide as the main analysis object, comparative study of the NJOY program input module parameters of the cross-section library production processing time, the integral amount of ΔKeff and sensitivity, the optimal input parameter selection program. The results of the benchmark examples show that the multi-group database is correct and the Keff calculation accuracy is high, which can provide a data basis for the uniform calculation of PWR fuel assemblies.