摘要
为了对“在技术上实现减轻放射性后果的场外防护行动是有限的甚至是可以取消的”这一基本目标进行量化评价,本文从简化事故后场外应急的角度,提出了严重事故后“3 km外不需要撤离、5 km外不需要隐蔽及服碘”的设计目标。结合漳州核电厂的厂址条件,推导出了一套用于漳州核电厂的严重事故后放射性后果评价准则。通过对“华龙一号”典型严重事故过程及放射性释放过程进行分析,结果表明,漳州核电厂“华龙一号”堆型满足本文提出的放射性后果评价准则,能够实现在严重事故后“3 km外不需要撤离、5 km外不需要隐蔽及服碘”的目标。
In order to quantitatively evaluate the basic objective of“offsite protective actions that can reduce the radiological consequences technically are limited or even can be cancelled”,this paper proposes the design objective of“no evacuation is required beyond 3 km,no concealment and iodine taking are required beyond 5 km”after severe accidents from the perspective of simplifying off-site emergency after accidents.Combined with the site conditions of Zhangzhou NPP,a set of radioactive consequence evaluation criteria for Zhangzhou NPP are derived.Through the analysis of the typical severe accident process and radioactive release process of HPR1000,the results show that the HPR1000 reactor type of Zhangzhou NPP meets the radiological consequence evaluation criteria proposed in this paper,and can achieve the goal of“no evacuation is required beyond 3 km,no concealment and iodine taking are required beyond 5 km”after a severe accident.
作者
邢继
石雪垚
黄树明
Xing Ji;Shi Xueyao;Huang Shuming(China Nuclear Power Engineering Co.,Ltd.,Beijing,100840,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2022年第6期122-127,共6页
Nuclear Power Engineering
关键词
华龙一号
严重事故
放射性源项
简化应急
HPR1000
Severe accident
Radioactive source term
Emergency simplification