我国核电机组核事故应急后场址补救剂量准则研究  

Study on Dose Criteria for Site Remediation after a Nuclear Accident Emergency in Nuclear Power Units in China

作　　者：于红[1] 刘汀 程诗思 吴怡睿 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,四川 成都

出　　处：《核科学与技术》2022年第4期204-211,共8页Nuclear Science and Technology

摘　　要：我国即将迎来核电机组批量退役的紧迫问题,同时我国核电场址多是滨海多机组场址、土地珍贵。如果核电机组发生核事故,计划一体化的机组退役与场址补救方案将是尽快恢复不低于事故前供电负荷需求最有效率的手段。为了解决这一问题,通过对国际原子能机构(IAEA)和美国核事故应急后场址补救准则的对比分析,参考韩国的监管实践,提出了可用于我国核电机组核事故应急后场址补救目的的剂量准则。这一剂量准则分别对不太可能授权补救行动、可用于使不受限解控场址最优化、可用于限制条件成功时使受限解控场址最优化、可用于限制条件失败时受限解控场址、不太可能授权解控场址的剂量范围做出了规定。Decommissioning of nuclear power units in bathes is an urgent problem to be faced in China;at the same time, most of China’s nuclear power sites are multi unit sites on the coast, and the land is rare. If nuclear accidents occur in nuclear power units, an integrated approach to planning remediation of site undergoing decommissioning of units will be the most efficient means to restore the power supply load not lower than the demand before the accident as soon as possible. To solve this problem, by analyzing comparatively the criteria for site remediation after a nuclear accident emergency in International Atomic Energy Agency (IAEA) and in the United States, and referring to the regulatory practice of Republic of Korea, the dose criteria for site remediation after a nuclear accident emergency in nuclear power units in China are proposed. The dose criteria specify respectively the dose region where a remedial action is unlikely to be warranted, the dose region of optimization for unrestricted site release, the dose region of optimization for restricted site release if restrictions succeed, the dose region of restricted site release if restrictions fail, the dose region where release of a site is unlikely to be warranted.

关 键 词：核电机组 核事故应急 场址补救 场址解控 机组退役 剂量准则 

分 类 号：TM6[电气工程—电力系统及自动化]