摘要
使用截面加工程序NJOY生成以针对最新释放的ENDF/B-VII和CENDL-3.1评价核数据截面库为基础库的2个ACE格式的温度相关中子截面库。使用压水堆多普勒数值基准题对生成的2个ACE格式截面库进行基准验算。验算结果表明,所生成的2个温度截面库在有效增殖系数、多普勒反应性亏损、多普勒反应性系数方面均与原基准题吻合良好,说明评价核数据截面库ENDF/B-VII和CENDL-3.1能很好地应用于ACE格式的截面库的制作。
Using the cross section processing procedures NJOY, two temperature-dependent neutron cross section libraries with the ACE（A Compact ENDF） format are generated based on the latest released ENDF/B-VII and CENDL-3.1, and are verified by PWR Doppler numerical benchmark problems. The results showed that these two cross section libraries were in good agreement with the original benchmark problems in the effective multiplication factor, Doppler reactivity loss and Doppler reactivity coefficient, which indicated that the two cross section libraries ENDF/B-VII and CENDL-3. lcan be used in the production of ACE format cross section libraries.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2012年第3期12-16,共5页
Nuclear Power Engineering
