CAJ | 학술논문

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ΔKef 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，Kef 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。
기우최신석방적ENDF/B-VII.1핵평개고，채용핵수거가공처리정서NJOY-99제작기우WIMS격식적다군수거고，침대경수퇴(Light Water Reactor, LWR)기본연료책원균균화계산기준제，이235U、238U핵소위주요분석대상，대비연구료NJOY정서수입모괴삼수적선택대절면고제작가공시간、적분량ΔKef 급령민도적영향，득도우화적수입삼수선택방안。기준례제험증결과표명：소제작적다군수거고시정학적，Kef 계산정도교고，가위압수퇴연료조건균균화계산제공수거기출。
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.