Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea.

IF 1.4 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES Journal of Radiological Protection Pub Date : 2024-03-28 DOI:10.1088/1361-6498/ad35d0
Minwoo Kwak, Hyeok Jae Kim, Ga-Eun Oh, Sang Won Shin, Kwang Pyo Kim
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Abstract

In Korea, decommissioning of nuclear power plants and transportation of the decommissioning waste are expected to expand in the near future. It is necessary to confirm that radiological risks to the public and workers are not significant through radiological safety assessment. The objective of this study is to assess the radiological safety for transportation of RPV waste, which is a major decommissioning waste with relatively high level of radioactivity. It was assumed that the waste would be transported to the Gyeongju disposal facility by land transportation. First, the source term and transportation method of the RPV waste were determined, and the external dose rates from the waste were calculated using MCNP. Then, transportation scenarios were assumed under both normal and accident conditions. Under the scenarios, radiation doses were calculated using the RADTRAN. Under normal operation scenarios without a transportation accident, assuming 40 shipments per year, the average individual doses for the public ranged from 6.56×10-6to 2.18×10-2mSv yr-1. The maximum individual doses for only a single shipment ranged from 2.43×10-6to 3.14×10-1mSv. For cargo handlers and vehicle crew members, the average doses were 2.26×101mSv yr-1and 2.95 mSv yr-1, respectively. Under transportation accident scenarios, average individual radiological risks which are product of the radiation doses and the annual accident rates ranged from 1.14×10-11to 1.61×10-10mSv yr-1by transportation route segment when considering the transportation accident rate. Average individual doses assuming transportation accident occurrence ranged from 2.62×10-4to 1.42×10-3mSv. The maximum individual dose under accident conditions was 7.99×10-2mSv. The calculated doses were below the regulatory limits in Korea. However, relatively high doses were observed for cargo handlers and vehicle crew members because of conservative assumptions. This study results can be used as basic data for the radiological safety assessment for the decommissioning waste transportation in the future.

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韩国核电站退役期间反应堆压力容器运输的辐射安全评估。
在韩国,核电站的退役和退役废料的运输预计在不久的将来会扩大。有必要通过辐射安全评估确认对公众和工人的辐射风险不大。本研究的目的是评估 RPV 废物运输的辐射安全,这是一种放射性水平相对较高的主要退役废物。假定废物将通过陆路运输运往庆州处置设施。首先,确定了 RPV 废物的源项和运输方式,并使用 MCNP 计算了废物的外部剂量率。然后,假定在正常和事故两种情况下进行运输。在这些情况下,使用 RADTRAN 计算辐射剂量。在没有运输事故的正常运行情况下,假设每年运输 40 次,公众的平均个人剂量为 6.56×10-6 至 2.18×10-2 mSv yr-1。单次运输的最大个人剂量介于 2.43×10-6 到 3.14×10-1 mSv 之间。货物装卸人员和车辆乘员的平均剂量分别为 2.26×101 mSv yr-1 和 2.95 mSv yr-1。在运输事故情况下,考虑到运输事故率,各运输线路段的平均个人辐射风险(辐射剂量与年事故率的乘积)介于 1.14×10-11 至 1.61×10-10 mSv yr-1 之间。假设发生运输事故的平均个人剂量为 2.62×10-4 至 1.42×10-3 mSv。事故条件下的最大个人剂量为 7.99×10-2 mSv。计算得出的剂量低于韩国的监管限值。然而,由于保守假设,货物装卸人员和车辆乘员的剂量相对较高。该研究结果可作为未来退役废物运输辐射安全评估的基础数据。
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来源期刊
Journal of Radiological Protection
Journal of Radiological Protection 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
2.60
自引率
26.70%
发文量
137
审稿时长
18-36 weeks
期刊介绍: Journal of Radiological Protection publishes articles on all aspects of radiological protection, including non-ionising as well as ionising radiations. Fields of interest range from research, development and theory to operational matters, education and training. The very wide spectrum of its topics includes: dosimetry, instrument development, specialized measuring techniques, epidemiology, biological effects (in vivo and in vitro) and risk and environmental impact assessments. The journal encourages publication of data and code as well as results.
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