摘要
为保证华龙一号堆内构件的结构完整性,在华龙一号首堆(福清核电厂5号机组)热态功能试验期间应对堆内构件的流致振动行为迚行现场实堆测量,开且需对现场实堆测量中涉及的实测测点布置迚行论证分析。本文将华龙一号堆内构件与M310堆型堆内构件的结构和流场迚行了对比,得出需要布置测点的新结构位置以及相同结构的薄弱位置;通过对华龙一号堆内构件比例模型试验结果的分析,找出流致振动相对薄弱的结构,在实堆上重点布点测量薄弱结构,其余位置在实堆上考虑少量测点迚行验证性测量;对于以上提到的薄弱位置以及考虑到实堆感应器测点失校的可能性,适当地考虑测点的冗余。通过与同类核电厂流致振动测量的比较,结果表明,华龙一号确定的测量结构、测点布置合理,开且该测点布置斱案已在福清核电厂5号机组实施。
In order to ensure the integrity of HPR1000 Reactor Internals(RI),on-site Flow induced vibration(FIV)measurement of RI should be performed in the hot functional test of unit 5 in Fuqing nuclear power plant which is the first reactor of HPR1000,and the arrangement of measure points should be demonstrated.RI structures and flow distribution of HPR1000 and M310 are compared in this paper.Based on the comparison,measurement points in new structures and weak locations in the same structures which need measurement are confirmed.Based on the analysis of HPR1000 RI scale model test results,the weak locations of FIV are found.The measurement of these weak locations will be critical and be arranged more measurement points in the actual measurement.For these weak locations,in case of the failure of some sensors,redundancy of measurement points in weak locations should be considered.Compared to the measurement of flow induced vibration in other reactor internals,the arrangement of the measurement points for flow induced vibration of HPR1000 reactor internals is reasonable.This plan was implemented in unit 5 of Fuqing Nuclear Power Plant.
作者
夏欣
喻丹萍
罗英
马建中
李燕
李浩
黄宗仁
Xia Xin;Yu Danpin;Luo Ying;Ma Jianzhong;Li Yan;Li Hao;Huang Zongren(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Reactor Engineering Research Institute,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第A01期55-58,共4页
Nuclear Power Engineering
关键词
华龙一号
堆内构件
流致振动
测点布置
论证
HPR1000
Reactor internals(RI)
Flow induced vibration(FIV)
Arrangement of measurement point
Demonstration
