蒙卡程序计算临界基准题测试检验ENDF/B-VIII.0核数据库

Monte Carlo calculation of critical benchmarking models for testing ENDF/B-VIII.0 nuclear data

  • 摘要: 采用MCNP程序和ENDF/B-VII.1,ENDF/B-VIII.0核数据库,对119个模型构成的临界基准题进行了临界计算测试检验。此临界基准题模型包含233U、高浓铀、中浓铀、低浓铀和钚材料的临界实验系统,中子能量覆盖了快中子、中能中子和热中子能谱。采用ENDF/B-VIII.0核数据库的计算有效增殖因子keff结果与基准实验结果相对偏差的均值和标准差分别为−68.98×10−5和407.88×10−5,检验计算keff结果与基准实验结果的偏差与基准实验不确定度比值在1σσ为标准不确定度)以内、1σ~3σ区间和大于3σ的数量分别为107,9和3个;将此结果与相同条件下ENDF/B-VII.1核数据库的计算结果进行了比较,表明ENDF/B-VIII.0核数据库对临界计算更准确,与实验模型结果符合更好。

     

    Abstract: The MCNP program and the ENDF/B-VII.1, ENDF/B-VIII.0 nuclear data were used to calculate the criticality respect to the critical benchmarking suits of 119 models for nuclear data testing. The benchmarking suits consists of 233U, high-enriched uranium, intermediate enriched uranium, low-enriched uranium and Pu critical configurations in fuel type, covering the spectra of fast, intermediate, and thermal neutrons. With ENDF/B-VIII.0 nuclear data, the average and standard deviation of the relative deviation between the calculation keff and the benchmarking keff were −68.98×10−5 and 407.88×10−5 respectively, and the tallies that the ratio of deviation to experimental uncertainty within 1σ, among 1σ–3σ and beyond 3σ were 107, 9 and 3, respectively. The resultant data were compared to the calculation results with ENDF/B-VII. 1 in the same computation conditions, which indicates that the ENDF/B-VIII.0 nuclear data was more accurate, and more consistent with the benchmarking results for criticality calculation.

     

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