This paper is devoted to the research on the radiation shielding calculations using Monte Carlo method.

本文主要应用蒙特卡罗方法进行了屏蔽计算的研究。

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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。

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This paper discussed the importance as well as the method of considering the resonance self-shielding effect in hybrid blanket and fast reactor neutron multigroup calculations.

本文讨论了在混合堆和快堆的多群中子输运计算中，考虑共振自屏效应的重要性及其考虑方法。

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