不同235U快裂变缓发中子群参数比较和验证

Comparison and Validation of Different 235U Fast Fission Delayed Neutron Group Parameters

  • 摘要: 分析了ENDF/B7、JEFF3.1、JENDL3.3、CENDL2.2及Keepin数据中的235U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。

     

    Abstract: The differences between 235U fast fission delayed neutron group parameters in ENDF/B7, JEFF3.1, JENDL3.3, CENDL2.2 and 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 3.1 are better than six-group delayed neutron parameters in other databases.

     

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