摘要
介绍了田湾核电站水-水高能反应堆(VVER)机组松脱部件监测系统(LPMS)的设计和设备结构组成,描述了其设计与美国核管会(NRC)RG1.133相关条款要求的差异。基于这些差异以及VVER机组的特殊性,分析了拟采取的改进措施存在的困难和不利影响。为执行与NRC RG1.133中安全要求相当的功能,在田湾核电站3号机组调试阶段开展了LPMS系统的功能补充试验,获取与压力容器相关的传感器信号的响应,验证了目前的传感器布置方式能满足NRC RG1.133的设计要求。
The design and structure specificities of loose part measurement system(LPMS) of VVER in Tianwan Nuclear Power Plant, as well as the differences of LPMS with the item NRC RG1.133, are introduced. The difficulties and the negative influence are analyzed based on these differences and the specificities of VVER, when the improvement is conducted. In order to implement the function like what NRC RG1.133 requested, additional tests of LPMS were carried out during the commissioning of Unit 3 in Tianwan Nuclear Power Plant. The signal response of the sensors related to the reactor pressure vessel(RPV) was detected successfully in the tests, and it was proved that the arrangement of the LPMS sensors could meet the design requirement of NRC RG1.133.
作者
朱军
周正平
刘文超
Zhu Jun;Zhou Zhengping;Liu Wenchao(CNNP Jiangsu Nuclear Power Corporation,Lianyungang,Jiangsu,222000,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2018年第5期117-121,共5页
Nuclear Power Engineering