压水堆MATXS格式数据库研制与验证  

Fabrication and Validation of PWR MATXS Nuclear Data Library

作　　者：霍小东 

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《核科学与工程》2014年第4期454-461,共8页Nuclear Science and Engineering

基　　金：大型先进压水堆及高温气冷堆核电站科技重大专项(2010ZX06206-02)

摘　　要：美国国家核数据中心(NNDC)已经正式发布了ENDF/B-VII评价核数据库,为了在压水堆核电厂设计和运行服务中应用国际上最新的评价核数据库研究成果,本文采用NJOY核数据库处理程序系统,研制了MATXS格式数据库。为了提高数据库制作效率、减少输入错误,本文研制了自动化NJOY输入文件生成程序AGNI,使用该程序完成了MATXS238的研制。并使用离散纵标程序DORT和ANISN对数据库进行了验证,验证结果表明:理论计算结果和实验值符合良好,可用于工程设计。本文为基础性的研究工作,制作数据库的方法可以推广到更前沿的反应堆研究领域和临界安全分析领域,此数据库的研制为先进反应堆(如次临界能源堆,超临界水堆、快堆等)研究、设计以及临界安全分析奠定了基础。The ENDF/B-VII has been released by National Nuclear Data Center（NNDC）.In order to use the latest evaluated nuclear data file in the PWR nuclear power plant design and operational technical support,a MATXS nuclear data library has been fabricated using the NJOY processing code.An AGNI code has been coded to generate automatically the input files of NJOY code.A MATXS238 nuclear data library has been fabricated using AGNI and NJOY code.The MATXS238 has been validated using the DORT and ANISN code through experiments and benchmarks.The results of validation show that a good agreement has been observed and the MATXS238 nuclear data library can be used in the nuclear power plant engineering design and criticality analysis.Also the method of generating the MATXS nuclear data library can be used in the nuclear data library fabrication of advanced nuclear reactor（such as,subcritical energy reactor,supercritical water reactor,fast breeder reactor,etc.）and criticality analysis.

关 键 词：ENDF/B-VII MATXS 压水堆 核数据库 先进反应堆 

分 类 号：TL329.3[核科学技术—核技术及应用]