HENDL1.1/MG数据库和VisualBUS1．0程序的临界基准计算与分析
Numerical Testing of HENDL1.1/MG Data Library and VisualBUS1.0 Code with Evaluated Critical Safety Benchmark Experiments
-
摘要: 使用自主开发的一维输运／燃耗／可视化计算程序系统VisualBUS1．0和HENDL1．1／MG数据库，对^233U，^235U和^239Pu的热溶液临界球基准实验和^237Np，^241Am和^244Cm的金属快裂变临界球问题进行校核。和国际上广泛使用的各种程序和数据库的模拟计算结果以及相关实验结果进行综合对比和分析，初步验证了HENDL1．1／MG中裂变核素核数据的可靠性和应用性，同时也进一步证明了VisualBUS1.0程序的正确性。The evaluated critical safety benchmark experiments including some major elements of fission materials, such as ^233U, ^235U, ^239pu and ^237Np, ^241Am, ^244Cm, were simulated using the home-developed one-dimensional
trasportation/burnup/optimization code system VisualBUS1.0 and HENDL1.1/MG, a multi-group working library of fusion-fission Hybrid Evaluated Nuclear Data Library, by FDS team. By the comparison with the measured resuits and the calculated values given in the International Handbook of Evaluated Criticality Safety Benchmark Experiments, HENDL1.1/MG data library and VisualBUS1.0 code are validated and qualified to be reliable.Abstract: The evaluated critical safety benchmark experiments including some major elements of fission materials, such as ^233U, ^235U, ^239pu and ^237Np, ^241Am, ^244Cm, were simulated using the home-developed one-dimensional
trasportation/burnup/optimization code system VisualBUS1.0 and HENDL1.1/MG, a multi-group working library of fusion-fission Hybrid Evaluated Nuclear Data Library, by FDS team. By the comparison with the measured resuits and the calculated values given in the International Handbook of Evaluated Criticality Safety Benchmark Experiments, HENDL1.1/MG data library and VisualBUS1.0 code are validated and qualified to be reliable.
下载: