基于WIMS格式多群核数据制作过程的优化分析  

Optimization analysis of the production process based on WIMS format multigroup nuclear data

作　　者：谢明亮[1] 陈玉清[1] 于雷[1] 时浩[1] 

机构地区：[1]海军工程大学核能科学与工程系,武汉430033

出　　处：《核技术》2015年第11期73-79,共7页Nuclear Techniques

摘　　要：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。Background：NJOY is used widely nuclear data processing program that can convert the data format of ENDF/B nuclear database into WIMS format of the multi-group cross section database.Purpose： This study aims to produce a multi-group database of WIMS-D format on the basis of the latest release of nuclear evaluation library ENDF/B-VII.1 by using nuclear data processing program NJOY-99.Methods： In allusion to basic fuel cell homogenization calculation benchmark problem of the light water reactor （LWR）, taking the 235U and 238U nuclide as the main objects of analysis, the effect on processing time of making cross section library, as well as integral parametersΔKef and data sensitivity of selecting input parameters of the NJOY program were compared and analyzed, which optimized the option of input parameter. Results and Conclusion：The results of validating on benchmark problems showed that the production of the multi-group database was correct, which embodied the high accuracy of calculation and provided the basis data of fuel assembly homogenization calculation for pressurized water reactor.

关 键 词：ENDF/B-VII.1 NJOY-99 核数据库 

分 类 号：TL99[核科学技术—核技术及应用]