Radiation shielding calculations on spent fuel casks are an inherent part of the nuclear analyses performed for the site safety report (SSR) when siting an interim spent fuel storage facility (ISFSF). The basis for this is a legislative requirement that the licensee must demonstrate to the nuclear regulator that no member of the public will be exposed to a radiation health risk as result of the operation of the ISFSF. Because of the enormous number of isotopes that are generated as result of the operation of a nuclear reactor, shielding calculations have to perform the following analyses which are the objectives of this research paper: (a) identify a group/set of nuclides that are important in radiation shielding with a view to ensuring that the shielding material/strategy adopted envelops the radiation emissions of all nuclides so as to prevent a deficiency in the radiation protection measures adopted (i.e. optimisation of protective measures); (b) determine the mathematical expression that links the behaviour (i.e. growth or decay) as a function of time within a stipulated time frame (i.e. the boundary conditions); (c) develop a mechanism for ranking nuclide importance in shielding; (d) determine whether there is a relationship between taking credit for burnup or not (Leotlela et al., 2015; Leotlela et al., 2020) and the resulting effective dose; and (e) determine whether there is a relationship between the effective dose and the duration of cask storage in the ISFSF.

在为临时乏燃料贮存设施 (ISFSF) 选址时，对乏燃料容器进行辐射屏蔽计算是为场址安全报告 (SSR) 进行的核分析的一个固有部分。其基础是一项立法要求，即许可证持有者必须向核监管机构证明任何公众成员都不会因 ISFSF 的运作而面临辐射健康风险。由于核反应堆运行会产生大量同位素，因此屏蔽计算必须执行以下分析，这是本研究论文的目标：(a) 确定对辐射屏蔽很重要的一组/一组核素，以确保所采用的屏蔽材料/策略包含所有核素的辐射发射，从而防止所采用的辐射防护措施出现缺陷（即优化保护措施）；(b) 在规定的时间范围内（即边界条件）确定将行为（即增长或衰减）作为时间函数联系起来的数学表达式；(c) 制定屏蔽核素重要性排序机制；(d) 确定是否将燃耗归功于功劳（Leotlela 等人，2015 年；Leotlela 等人，2020 年）与由此产生的有效剂量之间是否存在关系；(e) 确定有效剂量与 ISFSF 中木桶储存的持续时间之间是否存在关系。