摘要
为满足聚变 裂变次临界混合堆设计和其他相关研究的需要 ,以世界几个主要基本评价核数据库为数据来源 ,通过优选建立了名为HENDL1 .0 /E的多用途核数据库 ,采用国际通行的核数据库处理程序系统NJOY和TRANSX等程序制作了相应的工作数据库 ,其中包括多能群输运截面库HENDL1 .0 /MG、连续能量点状输运截面库HENDL1 .0 /MC、燃耗数据库HENDL1 .0 /BU和响应函数库HENDL1 .0 /RF ,利用世界上流行的中子输运程序对已有的一系列基准检验实验进行模拟计算和比较分析以检验混合库HENDL1 .0的正确性和有效性。
To meet the requirements of fusion-fission sub-critica l hybrid reactor design and the other related studies, the evaluated nuclear data library named HENDL1.0/E has been constituted based on the several main nationa l evaluated data libraries. The relevant working libraries including transport s ub-libraries HENDL1.0/MG in groupwise form, HENDL1.0/MC in pointwise form, an d the burnup sub-library HENDL1.0/BU and response function sub-library HENDL1. 0/RF are generated using the nuclear data processing codes NJOY97 and TRANSX2. T he simulating calculation and comparative analysis are carried out against a ser ies of existing benchmark test experiments with popular neutron transport codes , in order to validate the correctness and availability of the HENDL1.0.
出处
《核科学与工程》
CSCD
北大核心
2004年第4期366-376,共11页
Nuclear Science and Engineering
基金
国家自然科学基金资助项目 (10 175 0 6 8)
中科院知识创新工程项目资助
