摘要
压水堆核电厂停堆开盖时刻主冷却剂放射性浓度限值是核电厂的重要设计参数。本文基于停堆开盖后厂内辐射风险来源分析,建立了适用于压水堆核电厂停堆压力容器开盖时刻主冷却剂中的放射性浓度控制值评估方法,并采用欧洲第三代压水堆技术方案(EPR)堆型核电厂的设计参数对建立的方法进行了验证。验证结果表明:基于此方法得出的停堆开盖限值与EPR堆型核电厂原设计较接近。
The limits of radioactivity concentration in primary coolant during the time of the pressure vessel head opening for shutdown are the important design parameters of PWR,which lack the design methodology in a long time.In this paper,the evaluation methods of radioactive concentration control value in the primary coolant during the time of RPV opening are established for PWR,based on the analysis of the sources of radiation risks after pressure vessel head opening,.This methodology has been verified by comparing with original ERP design results.
作者
黄倩倩
吕炜枫
熊军
HUANG Qianqian;LV Weifeng;XIONG Jun(China Nuclear Power Design Co.Ltd.,Guangdong Shenzhen,518026)
出处
《辐射防护》
CAS
CSCD
北大核心
2019年第5期391-395,共5页
Radiation Protection
关键词
停堆开盖
冷却剂
浓度限值
压水堆核电厂
辐射风险
RPV head opening in shutdown
coolant
concentration limit
PWR
radiation risk
