| 摘要: |
| 目的 在移动式反应堆现有研发水平无法满足《放射性物品安全运输规程》(GB 11806—2019)的背景下，本研究提出通过风险评价的方法对移动式反应堆运输的安全性进行研究。方法 风险评价的内容主要包括计算移动式反应堆在运输中遇到假想事故的概率和事故后果，本研究根据美国联邦法规10CFR71中§12条款的相关要求对移动式反应堆在运输中可能遇到的事故种类进行梳理，并以事故后果最为严重的与油罐车发生撞击作为极端的假想事故，通过五因子计算公式的方法对假定热功率为20 MWt的移动式反应堆在假想事故下的事故后果进行计算。结果 计算得出移动式反应堆在每年运输1次的条件下假想事故的发生概率为9.7×10–6次/年，反应堆冷却1年后在假想事故下对工作人员的辐照剂量为810 mSv;冷却5年后在假想事故下对工作人员的辐照剂量为590 mSv。结论 假想事故下移动式反应堆的事故后果远超过Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material(SSG-26)和《电离辐射防护与辐射源安全标准》(GB 18871—2002)中工作人员受到的辐照剂量限值，并且假想事故的发生概率没有满足我国核安全导则对超设计基准事故10–7次/年的筛选要求。因此有必要在移动式反应堆运输过程中采取包括武装押运和路线规划在内的管理措施以降低假想事故的概率并采取相应的应急措施减轻假想事故的事故后果以满足核安全部门的监管要求。 |
| 关键词: 移动式反应堆 反应堆运输 事故分析 辐射安全 |
| DOI：10.19554/j.cnki.1001-3563.2024.21.008 |
| 分类号: |
| 基金项目: |
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| Safety Risk Assessment of Mobile Microreactor Transportation |
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YAN Fengzhe, ZHAO Qiang, LIU Jialing, ZHU Zhigang, ZHANG Futong
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(China Nuclear Power Engineering Co., Ltd., Beijing 100840, China)
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| Abstract: |
| In view of the fact that the current R&D level of mobile microreactor cannot meet the requirements of the GB11806-2019 Regulations for the Safe Transport of Radioactive Materials , the work aims to study the transportation safety of mobile microreactor by means of risk assessment. The risk assessment mainly included calculating the probability and consequences of extreme accidents encountered by the mobile microreactor during transportation, and the types of accidents that the mobile microreactor might encounter during transportation were sorted out according to the relevant requirements of 10CFR71 and §12 of the United States. The collision with the tanker truck with the most serious accident consequences was taken as the extreme hypothetical accident and the accident consequences of the mobile microreactor with a hypothetical heat power of 20 MWt under a hypothetical accident were calculated by the method of five-factor formula. The hypothetical accident probability of the mobile microreactor was 9.7×10–6/year under the condition of annual transportation, and the irradiation dose to the workers under the hypothetical accident after the microreactor was cooled for one year was 810 mSv. After 5 years of cooling, the radiation dose to the workers under a hypothetical accident was 590 mSv. The consequences of the mobile microreactor under the hypothetical accident far exceed the irradiation dose limits for workers in SSG-26 Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material and the GB 18871—2002 Safety Standard for Protection against Ionizing Radiation and Radiation Sources . Moreover, the probability of hypothetical accidents does not meet China's nuclear safety guidelines screening requirement of 10–7/year for beyond design basis accidents. Therefore, it is necessary to take management measures, including armed escort and route planning, during the transportation of mobile microreactors, to reduce the probability of hypothetical accidents, and to take corresponding emergency measures to mitigate the accident consequences of hypothetical accidents to meet the regulatory requirements of the nuclear safety authorities. |
| Key words: mobile microreactor transportation of microreactor accident analysis radiation safety |
