中低放废物处置设施放射性废物检查楼退役废物辐射工作人员暴露剂量评估

Rin-Ah Kim, Dho Hoseog, K. T. man, C. Cho
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引用次数: 1

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这是一篇在知识共享署名非商业许可(http://creativecommons.org/licenses/ by-nc/3.0)条款下发布的开放获取文章,该许可允许在任何媒体上不受限制地进行非商业使用、分发和复制。韩国放射性废物厅计划,为解决第1阶段处置设施的放射性废物接收和储存大楼缺乏检查空间和滚筒处理空间的问题,建设放射性废物检查大楼,扩大放射性废物的储存能力。在本研究中,使用蒙特卡洛n粒子输运代码计算了在放射性废物检查大楼储存区内处理退役废物新处置容器的辐射工作人员的暴露剂量。304个新处置容器的年集体剂量总计为84.8人毫西弗,辐射工作估计每年工作时数为306小时。当304个新的处置容器(小型/中型)存放于贮存区时,发现有25名辐射工作人员需要接受/处置检查,估计每个工作人员的年平均暴露剂量为3.39 mSv。辐射工作人员在高辐射剂量区操作小容器时,应通过增加混凝土衬里厚度对小容器进行进一步屏蔽,以提高辐射工作人员的工作效率和辐射安全。本研究结果将有助于根据实际测量结果,利用退役废物的源项和特征,为辐射工作人员建立最佳的辐射工作条件。
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The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility
This is an Open-Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/ by-nc/3.0) which permits unrestricted non-commercial use, distribution, and reproduction in any medium, provided the original work is properly cited The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.
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