基于CXROS平台的CMGS1.0核截面数据库研制与验证  

Development and Verification of CMGS1.0 Library Based on the CXROS Nuclear Data Processing Program

作　　者：杨寿海 曹南凤 刘杰 祖铁军 徐宁 YANG Shouhai;CAO Nanfeng;LIU Jie;ZU Tiejun;XU Ning(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,China Nuclear Power Engineering Co.,Ltd,Shenzhen of Guangdong Prov.518172,China;School of Nuclear Science and Technology,Xi'an Jiaotong University,Xi'an of Shaanxi Prov.710049,China)

机构地区：[1]中广核工程有限公司核电安全监控技术与装备国家重点实验室,广东深圳518172 [2]西安交通大学核科学与技术系,陕西西安710049

出　　处：《核科学与工程》2024年第6期1410-1418,共9页Nuclear Science and Engineering

基　　金：国家重点实验室项目(项目名称:MATXS格式输运核截面处理与工程验证技术,项目编码:K-A2018.424)的经费支持

摘　　要：基于中广核工程有限公司与西安交通大学在NECP-Atlas程序基础上联合开发的MATXS格式多群截面加工平台CXROS,采用ENDF/B-Ⅶ.1评价库,研制了适用于压水堆核电厂和干法贮存容器屏蔽设计的174群中子、38群光子的MATXS格式多群截面数据库CMGS1.0。该库选用权重谱IAEA weight function以及勒让德P3近似,共振自屏修正采取10组背景截面。该库含有293 K、600 K、900 K温度下的截面数据。采用SN程序以及SINBAD屏蔽基准题库的ASPIS基准题和NAIADE基准题进行基准验证。验证结果表明,CMGS1.0输运库在上述基准题中的C/E最大值为1.18,平均值为0.89,表明CMGS1.0输运库可应用于轻水堆核电厂的屏蔽计算。本工作可为屏蔽截面数据的加工和验证提供借鉴。A MATXS format multi-group library set named CMGS1.0 with 174-neutron group and 38-photon group based on ENDF/B-Ⅶ.1 evaluated nuclear data and MATXS format multi-group cross-section processing platform CXROS jointly developed by China Nuclear Power Engineering Co.,Ltd and Xi'an Jiaotong University and based on NECP-Atlas program.CMGS1.0 library is used for the shielding design of PWR NPP and spent fuel dry storage container.Weight function of the multi-group library set is taken from the IAEA library and the max legendre order of scattering matrix is three.10 Bondarenko background cross sections are used for generating the self-shielded multi-group cross sections.The library is generated under 293 K,600 K and 900 K.SN program and SINBAD shielding benchmarks are used to verify the validation of the library.The verification results show that the maximum C/E value of CMGS1.0 library is 1.18 and the average value is 0.89,which indicates that CMGS1.0 library can be applied to shielding calculation of light water reactor.This work can provide reference for the processing and verification of cross-section data for shielding.

关 键 词：ENDF/B-Ⅶ.1评价库 MATXS格式多群截面数据库 SN程序 SINBAD屏蔽基准题 

分 类 号：TL48[核科学技术—核技术及应用]