辐射防护通讯 ›› 2024, Vol. 44 ›› Issue (2): 8-14.

• 研究通报 • 上一篇    下一篇

HTR-PM高温气冷堆乏燃料贮存系统检修辐射防护研究

雷伟俊1, 史进1, 丁明2, 黄淑龙3   

  1. 1.华能核能技术研究院有限公司,上海 200126;
    2.中核武汉核电运行技术股份有限公司,武汉 430223;
    3.中国辐射防护研究院,太原 030006
  • 收稿日期:2023-12-20 出版日期:2024-04-20 发布日期:2024-05-17
  • 作者简介:雷伟俊(1986—),男,2011年毕业于西安交通大学核工程与核技术专业,高级工程师。E-mail:wj_lei@hntc.chng.com.cn
  • 基金资助:
    华能集团总部科技项目“HNKJ22-H01高温气冷堆燃料装卸系统运维技术研究”资助。

Study on radiation protection during the overhaul of HTR-PM spent fuel storage system

LEI Weijun1, SHI Jin1, DING Ming2, HUANG Shulong3   

  1. 1. Huaneng Nuclear Energy Technology Research Institute Co. Ltd., Shanghai 200126;
    2. China Nuclear Power Operation Technology Co. Ltd., Wuhan 430223;
    3. China Institute for Radiation Protection, Taiyuan 030006
  • Received:2023-12-20 Online:2024-04-20 Published:2024-05-17

摘要: 针对HTR-PM高温气冷堆乏燃料贮存系统设备检修时的辐射防护问题,建立了乏燃料贮罐及其相关舱室的三维模型,采用蒙特卡罗方法评估计算了工作人员检修位置处的γ剂量率。结果表明:剂量率随评估点位与混凝土平台开口之间距离的增加而快速降低;由于屏蔽罩和混凝土楼板存在孔洞,导致乏燃料装料间混凝土平台孔洞正上方剂量率较高,考虑2倍安全系数,距离孔洞中心50 cm范围内剂量率都处于红区范围,应严格限制人员进入此区域;检修设备间内距离孔洞中心30~70 cm范围内点位的剂量率处于限定工作区(橙区),人员在此区域内的工作时间应尽量缩短。为保障安全,建议开展实体模拟培训,缩短作业时间;设置厚度不小于16 cm的铅砂临时屏蔽体,穿戴防护装备;对局部热点去污以降低源项强度。

关键词: 高温气冷堆, 乏燃料贮存系统, 辐射防护, 蒙特卡罗

Abstract: In order to address the radiation protection during equipment maintenance and overhaul of HTR-PM high-temperature gas-cooled reactor (HTGR) spent fuel storage system, a three-dimensional model of the spent fuel storage tank and its related compartments was established. The gamma dose rate at staff maintenance location was calculated using the Monte Carlo method. The results show that: the dose rate decreases rapidly with the increase of the distance between the assessed point position and the opening of the concrete platform; due to the existence of holes on the shielding cover and the concrete floor slab, a high dose rate directly above the holes on the concrete platform of the spent fuel loading room was found. Considering the 2-fold safety coefficient, the dose rate is in the range of the red zone around 50 cm from the center of the holes, and the entry of personnel into the area should be strictly limited; the point of radiation protection in the service equipment room is in the range of 30-70 cm from the center of the holes. The dose rate within 30-70 cm from the center of the maintenance equipment room is in the restricted working area (orange zone), and the working time of the personnel in this area should be as short as possible. In order to ensure safety, it is recommended to carry out physical simulation training and shorten the working time, to set up a temporary shield of lead sand not less than 16 cm and protective equipment, and to decontaminate the local hot spots to reduce the intensity of the source term.

Key words: HTGR, spent fuel storage system, radiation protection, Monte Carlo methosd

中图分类号: 

  • TL75