ABSTRACT In connection with the accuracy of the 10B(n, α) cross section in the thermal- and epithermal-neutron energy regions, criticality calculation results were examined for six benchmark sets of light-water-moderation critical experiments of UO2 and MOX fuel lattice cores with un-borated and borated water. Two of the benchmark sets were those implemented in the Tank-Type Critical Assembly (TCA). The others were taken from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP), and the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP). The enrichments of the UO2 fuel range from 1.9 wt% to 2.6 wt%, and the Pu contents of the MOX fuel do from 2.0 to 6.6 wt%. The boron concentrations in water are up to 1511 ppm. The effective neutron multiplication factors (keff ) were taken from the published documents. They were calculated with continuous-energy Monte Carlo calculation codes in combination with JENDL-4.0, and other evaluated nuclear data libraries. It was confirmed that the keff values of the critical cores increased with the boron concentrations, which indicates that the 10B(n, α) cross section in the thermal- and epithermal-neutron energy regions should be larger than those in JENDL-4.0 and other libraries.

中文翻译：

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10B(n,α)截面硼酸水慢化实验岩心临界计算结果趋势

摘要 针对热中子和超热中子能区 10B(n, α) 截面的准确性，对六组 UO2 和 MOX 燃料晶格的轻水慢化临界实验基准的临界计算结果进行了检验。核心与未硼酸和硼酸水。其中两个基准集是在坦克型关键组件 (TCA) 中实施的。其他的取自国际评估临界安全基准实验手册 (ICSBEP) 和国际评估反应堆物理基准实验手册 (IRPhEP)。UO2 燃料的富集范围为 1.9 wt% 至 2.6 wt%，而 MOX 燃料的 Pu 含量为 2.0 至 6.6 wt%。水中的硼浓度高达 1511 ppm。有效中子倍增因子 (keff) 取自已发表的文件。它们是使用连续能量蒙特卡罗计算代码结合 JENDL-4.0 和其他评估的核数据库进行计算的。确定临界核的 keff 值随着硼浓度的增加而增加，这表明热和超热中子能区的 10B(n, α) 截面应大于 JENDL-4.0 和其他图书馆。