摘要
堆舱包容失效是判断应急状态升级的重要技术条件,是应急决策的重要技术依据。本文提出了采用舱室辐射水平作为堆舱包容失效判定依据的方法,确定了用于判定包容失效的可监测量(131I核素活度浓度和舱室γ剂量率),建立了舱室辐射水平与堆舱泄漏率之间的传递关系,并给出判据量值的计算方法。
The inclusion failure of the reactor compartment is an important technical condition for judging the upgrade of emergency state and an important technical basis for emergency decision.In this paper,a method using compartment radiation level as the basis for judgment of the inclusion failure of reactor compartment is proposed.The monitorable quantities(131I nuclide activity concentration andγdose rate of compartment)used to judge inclusion failure are determined,the transfer relationship between compartment radiation level and reactor leakage rate is established,and the calculation method of criterion value is given.
作者
林晓玲
汪林
Lin Xiaoling;Wang Lin(Unit 92609,Beijing,100077,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2024年第1期145-148,共4页
Nuclear Power Engineering
关键词
反应堆舱
包容失效
泄漏率
辐射监测
核事故
Reactor compartment
Inclusion failure
Leak rate
Radiation monitoring
Nuclear accident