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某压水堆核电厂辐射控制区氚化水蒸汽监测
引用本文:马来山,张志强,崔进,李文国.某压水堆核电厂辐射控制区氚化水蒸汽监测[J].辐射防护通讯,2020,40(6):35-38.
作者姓名:马来山  张志强  崔进  李文国
作者单位:广西防城港核电有限公司, 广西 防城港, 538001
摘    要:压水堆核电厂一回路冷却剂中的部分氚会通过废液和废气排放系统排放至工作环境中。本文报道某压水堆核电厂辐射控制区气态氚的监测结果:运行期间气态氚浓度范围为<LLD~9.21×102 Bq/m3;大修期间为<LLD~3.14×103 Bq/m3。监测结果显示,压水堆核电厂运行初期工作环境中氚浓度较低,工作人员在现场工作无需采取额外的防护措施以及进行氚内照射剂量监测。

关 键 词:压水堆核电厂  辐射控制区  氚化水蒸汽  
收稿时间:2020-09-15

Monitoring of Tritiated Steam in Controll Area of a PWR Nuclear Power Plant
Ma Laishan,Zhang Zhiqiang,Cui Jin,Li Wenguo.Monitoring of Tritiated Steam in Controll Area of a PWR Nuclear Power Plant[J].Radiation Protection Bulletin,2020,40(6):35-38.
Authors:Ma Laishan  Zhang Zhiqiang  Cui Jin  Li Wenguo
Affiliation:Guangxi Fangchenggang Nuclear Power Co. Ltd., Fangchenggang, Guangxi, 538001
Abstract:Some tritium in the primary coolant circuit of a pressurized water reactor can be discharged into the working environment through liquid waste and gas emission systems. The monitoring results of vaporous tritium in the controll area of a PWR nuclear power plant is presented. It comes out that, during operation and outrage, the concentration of vaporous tritium was <LLD-9.21×102 Bq/m3 and <LLD-3.14×103 Bq/m3 , respectively. This indicates the tritium concentration in the initial working environment is relatively low, and there is no need to take additional protective measures for working stuff and conduct tritium internal dose monitoring.
Keywords:PWR nuclear power plant  Controll area  Tritiated steam  
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