Calculation of Effective Coefficient of Spontaneity Fission Neutron Source in CFBR-Ⅱ Reactor
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摘要: 为计算CFBR-Ⅱ堆自发裂变中子源的有效强度,建立了有效系数的蒙特卡罗算法。分别抽样模拟自发裂变中子源与本征分布中子源的产生及其在系统内的输运过程,统计二者引起的泄漏中子计数,其比值即为该自发裂变中子源的有效系数。考虑到CFBR-II堆体结构的特殊性,对上下半球分区处理,采用栅元舍弃技巧计算得到堆体各处自发裂变中子源的有效系数,为堆体总的自发裂变中子有效强度计算提供了依据。Abstract: In order to calculate the effective intensity of spontaneity fission neutron source in CFBR-II reactor,Monte Carlo calculation method of effective coefficient is built.The naissance and transport process of spontaneity fission neutron and eigen distribution neutron are simulated.The effective coefficient of spontaneity fission neutron source equals to the ratio of leakage neutron number which come from two kinds of neutron sources.Considering the special structure of CFBR-II reactor,for the spontaneity fission neutron sources,the effective coefficient of different positions in upper hemisphere and lower hemisphere are calculated separately using cell-rejection technique.These results can be used as the basis to calculate the total effective intensity of spontaneity fission neutron source.
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