高氚内照射风险检修工作的辐射防护实践  

Radiation protection practice on maintenance with high risk of tritium internal exposure

作　　者：孙雷 杜烜境 王孔钊 刘玉龙[2] Sun Lei;Du Xuanjing;Wang Kongzhao;Liu Yulong(CNNP Nuclear Power Operations Management Co.,Ltd.,Jiaxing 314300,China;Clinical Diagnosis and Treatment Center of Oncology,the Second Affiliated Hospital of Soochow University,Suzhou 215004,China)

机构地区：[1]中核核电运行管理有限公司,嘉兴314300 [2]苏州大学附属第二医院肿瘤临床诊疗中心,苏州215004

出　　处：《国际放射医学核医学杂志》2024年第12期774-781,共8页International Journal of Radiation Medicine and Nuclear Medicine

摘　　要：高氚重水系统检修工作在重水反应堆中广泛开展, 大部分此类检修工作不仅存在γ外照射和放射性污染的风险, 更存在可能超出职业照射剂量限值的氚内照射风险。与外照射变化相对缓慢的特点相比, 高氚重水导致的空气中氚水平的变化迅速, 加之影响工作人员氚内照射剂量的因素很多, 因此建立一套完整的辐射工作控制流程对于应对这种风险的发生十分必要。笔者以CANDU-6型重水堆慢化剂主泵O型圈更换工作为例, 从工作控制、辐射风险分析、辐射防护方案制定、现场实施控制和实施效果分析等方面概述了高氚重水系统检修工作中的辐射防护方法, 以期为同类核设施的相关检修工作提供一定的借鉴和参考。The maintenance work of high tritium heavy water systems is widely carried out in heavy water reactors.Most of these maintenance work not only poses risks of gamma external radiation and radioactive contamination,but also risks of tritium internal radiation that may exceed the occupational exposure dose limit.Compared with the relatively slow changes in external exposure,the rapid changes in tritium levels in the air caused by high tritium heavy water,coupled with many factors that affect the tritium internal exposure dose of workers,make it necessary to establish a complete radiation control process to address this risk.The authors take the replacement of the O-ring of the moderator main pump in CANDU-6 heavy water reactor as an example,and summarize the radiation protection methods in the maintenance work of high tritium heavy water systems from the aspects of work control,radiation risk analysis,radiation protection plan formulation,on-site implementation control,and implementation effect analysis,in order to provide some reference and guidance for related maintenance work of similar nuclear facilities.

关 键 词：氚 重水堆核电厂 内照射 辐射防护 

分 类 号：TL7[核科学技术—辐射防护及环境保护] TM623[电气工程—电力系统及自动化]