压水堆核电厂压力容器开盖时刻主冷却剂放射性浓度控制要求研究

辐射防护 ›› 2019, Vol. 39 ›› Issue (5): 391-395.

压水堆核电厂压力容器开盖时刻主冷却剂放射性浓度控制要求研究

黄倩倩,吕炜枫,熊军

深圳中广核工程设计有限公司,广东深圳 518057

出版日期:2019-09-15 发布日期:2019-10-14
作者简介:黄倩倩(1987—),女,2009年毕业于东华理工大学核工程与核技术专业,工程师。E-mail:huangqianqian@cgnpc.com.cn

Study on primary coolant radioactivity requirement at the time of pressure vessel head opening in PWR

HUANG Qianqian, LV Weifeng, XIONG Jun

China Nuclear Power Design Co. Ltd., Guangdong Shenzhen, 518026

Online:2019-09-15 Published:2019-10-14

摘要/Abstract

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。

关键词: 停堆开盖, 冷却剂, 浓度限值, 压水堆核电厂, 辐射风险

Abstract: 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.

Key words: RPV head opening in shutdown, coolant, concentration limit, PWR, radiation risk

黄倩倩,吕炜枫,熊军. 压水堆核电厂压力容器开盖时刻主冷却剂放射性浓度控制要求研究[J]. 辐射防护, 2019, 39(5): 391-395.

HUANG Qianqian, LV Weifeng, XIONG Jun. Study on primary coolant radioactivity requirement at the time of pressure vessel head opening in PWR[J]. RADIATION PROTECTION, 2019, 39(5): 391-395.

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