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使用国际原子能机构的基准快堆例题BN-600对大型集成多功能中子学计算分析系统Visual BUS4.2进行了测试。与国际上其他单位的程序和数据库计算结果对比分析,其中有效增值因子(keff)、燃料多普勒系数(kDfuel)、径向膨胀系数(Rrad)、轴向膨胀系数(Rax)和有效缓发中子份额(βeff)的计算结果均介于其他单位测试值之间,验证了算法与各种材料的反应截面的可靠性。初步证明了Visual BUS4.2的蒙特卡罗输运模块与数据库在复杂反应堆核设计中的可靠性。但是由于密度系数本身比较小,各测试单位测试结果之间偏差都比较大,所以对密度系数还需进行进一步的分析与研究。
The use of the International Atomic Energy Agency benchmark fast reactor example BN-600 on a large integrated multi-functional neutronics calculation and analysis system VisualBus4.2 was tested. Compared with the results of other international programs and databases, the effective value-added (keff), kDfuel, Rrad, Rax and effective retardation The calculation results of neutron fraction (βeff) are all between the other unit test values, which verifies the reliability of the cross section between the algorithm and various materials. The reliability of the VisualBus4.2 Monte Carlo transport module and database in nuclear reactor design was initially proved. However, the density coefficient itself needs to be further analyzed and researched due to the relatively small deviation between the test results of the test units.