以某型乏燃料运输容器为计算模型,对其进行了临界安全、核热分布以及辐射屏蔽计算,并对临界计算和屏蔽计算的部分参数进行了敏感性分析。
Taking a spent fuel shipping cask as calculated model, detailed criticality safety, nuclear heat distribution and shielding calculations and sensitivity analysis of some parameters were performed.
以某型乏燃料运输容器为计算模型,对其进行了临界安全、核热分布以及辐射屏蔽计算,并对临界计算和屏蔽计算的部分参数进行了敏感性分析。
Taking a spent fuel shipping cask as calculated model, detailed criticality safety, nuclear heat distribution and shielding calculations and sensitivity analysis of some parameters were performed.
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