摘要
分析了ENDF/B7、JEFF3.1、JENDL3.3、CENDL2.2及Keepin数据中的235 U快裂变缓发中子群参数的差异,通过CFBR-Ⅱ堆超瞬发临界实验检验了这几套缓发中子数据的准确性。检验结果表明,用于计算反应堆反应性,Keepin缓发中子群参数仍比数据库数据准确;数据库数据中,JEFF3.1的8群结构数据好于其他数据库6群结构数据。
The differences between 235 U fast fission delayed neutron group parameters in ENDF/B7,JEFF3.1,JENDL3.3,CENDL2.2and Keepin datum were analyzed.The delayed neutron group parameters were validated by experiments on CFBR-Ⅱ.The Keepin delayed nutron group parameters are more accurate than delayed nutron group parameters in the primary nuclear databases.The eight-group delayed neutron parameters in JEEF 3.1are better than six-group delayed neutron parameters in other databases.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2011年第8期955-959,共5页
Atomic Energy Science and Technology