EPR核电机组核反应堆厂房临时空调通风系统方案研究应用被引量：1

Research and Application of Temporary Air Conditioning and Ventilation System Scheme for Nuclear Reactor Building of EPR Nuclear Power Plant

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摘要某EPR核电机组在换料大修期间,核岛核反应堆厂房(Reactor Building,HRA)内制冷系统DER因检修隔离阀需要停运,届时核岛将失去通风冷源,压力容器开盖后一回路水温仍有60℃-70℃,会持续对核岛内部环境进行传热,环境温度湿度会升高。据监测,环吊操作台温度达到38℃,穹顶区域温度达到45℃,高温高湿环境增加了作业人员中暑、表面玷污等作业风险。本文结合某EPR机组设计特点,采用实证研究的方法进行了EPR机组大修期间核岛临时通风设计方案可行性研究并应用。研究发现,大修通风冷源停运期间,在不破坏控制区边界和负压状态情况下,引入临时冷源,可以有效控制核岛内适宜作业的环境温度。 During the refueling outage of an EPR nuclear power unit,the cooling system DER in the reactor building(HRA)of the nuclear island needs to be shut down due to the maintenance of the isolation valve.At that time,the nuclear island will lose the cooling source of ventilation.After the pressure vessel is opened,the primary circuit water temperature will still be 60℃-70℃,which will continue to heat the internal environment of the nuclear island,and the ambient temperature and humidity will rise.According to the monitoring,the temperature of the ring crane operating platform reaches 38℃,and the temperature of the dome area reaches 45℃.The high temperature and high humidity environment increases the risk of heatstroke,surface contamination and other operations.Based on the design characteristics of an EPR unit,the feasibility study and application of the temporary ventilation design scheme of the nuclear island during the overhaul of the EPR unit are carried out with the method of empirical research.The study found that during the outage of the ventilation cold source,the introduction of temporary cold source can effectively control the ambient temperature suitable for operation in the nuclear island without damaging the boundary of the control area and the negative pressure state.

作者段宗辉李延韬毕斗斗 Duan Zonghui;Li Yantao;Bi Doudou(South China University of Technology,Guangzhou 510641,China;China Guangdong Nuclear Power Engineering Co.,Ltd.,Shenzhen 518000,China;Taishan Nuclear Power Joint Venture Co.,Ltd.,Jiangmen 529200,China)

机构地区华南理工大学中广核电工程有限公司台山核电合营有限公司

出处《核安全》 2023年第2期19-23,共5页 Nuclear Safety

关键词安全壳冷却通风系统控制区制冷机降温除湿 Containment cooling and ventilation system Control area refrigerator Cooling and dehumidification

分类号 TL48 [核科学技术—核技术及应用]

作者简介段宗辉(1990—),男,工程师,硕士研究生,现主要从事核电通风设备维修工作;通讯作者:毕斗斗,E-mail:ddbi@scut.edu.cn。