从源的角度探讨放射性核素污染材料在事故后修复中的应用

Pub Date : 2023-06-30 DOI:10.14407/jrpr.2022.00045
Kazuji Miwa, T. Iimoto
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引用次数: 0

摘要

背景:在探讨放射性核素污染土壤和辐射灾害产生的碎片利用可能性的过程中,有必要在考虑污染物质来源的同时,制定适当的辐射暴露防护管理策略。材料和方法:根据国际放射防护委员会的建议和国际原子能机构的安全标准,总结了可能适用于与源有关的方法的放射防护标准。我们提出了辐射防护的五种解释,有助于促进在事故后修复中使用部分低水平放射性核素污染土壤和碎片的可能性的讨论。解释一至解释三基于“在事故后康复中使用参考水平保护公众”的想法,而解释四和解释五基于“在计划活动中处理源时,在事故后康复中使用剂量限制保护公众”的想法。根据源的定义,前一种想法被细分为三种,这是由参考水平管理的,后一种想法被细分为两种,这取决于使用受污染物质的额外剂量是否被认为是可接受的。结果与讨论:为了验证五种解释的适用性,我们通过两个可行的案例提出了保护标准的具体价值。在本案例研究中,我们建议采用基于解释四的剂量限制进行辐射防护,并选择公众为1毫西弗/年,处理放射性核素污染材料的工作人员为20毫西弗/年。结论:我们具体和系统地展示了如何将辐射防护概念应用于讨论在国际防护体系框架内使用放射性核素污染材料的可能性的过程。本研究结果可为从辐射防护的角度探讨放射性核素污染材料作为辐射灾后恢复重建替代选择的可能性提供必要的信息。
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A Source-Related Approach for Discussion on Using Radionuclide-Contaminated Materials in Post-accident Rehabilitation
Background: In the process of discussion on the possibility of using radionuclide-contaminated soil and debris generated by radiation disasters, a strategy for the proper management of radiation exposure protection while considering the source of the contaminated materials is necessary.Materials and Methods: The radiological protection criteria that are likely to be applied to the source-related approach based on the International Commission on Radiological Protection recommendations and the International Atomic Energy Agency safety standards are summarized. We proposed five interpretations of radiation protection to contribute to the promotion of discussion on the possibility of using a part of low-level-radionuclide-contaminated soil and debris in the post-accident rehabilitation. Interpretations I to III are based on the idea of “using a reference level to protect the public in post-accident rehabilitation,” whereas IV and V are based on the idea of “using the dose constraint to protect the public in the post-accident rehabilitation when the sources are handled in a planned activity.” The former idea is subdivided into three based on the definition of the source, which is managed by the reference level, and the latter idea is divided into two depending on whether or not additional dose from using contaminated materials is deemed acceptable.Results and Discussion: To confirm the applicability of the five interpretations presented, we suggested the concrete values of protection criteria via two feasible cases. In this case study, we proposed radiation protection by the dose constraint based on the Interpretation IV and chose 1 mSv/yr for the public and 20 mSv/yr for workers dealing with radionuclide-contaminated materials.Conclusion: We concretely and systematically demonstrated how the concept of radiation protection can be applied to the process of discussion on the possibility of using radionuclide-contaminated materials within the framework of an international system of protection. This study’s findings can provide necessary information to discuss the possibility of using radionuclide-contaminated materials as an alternative option for recovery and reconstruction after a radiation disaster from the viewpoint of radiation protection.
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