压水堆核电厂堆内构件联接件防松性能振动考核试验  

Vibratory examination testing on anti-looseness performance of PWR internal fasteners

作　　者：梁星筠[1] 王赤虎[1] 高雷[1] 谢永诚[1] 杨仁安[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《中国工程机械学报》2009年第3期326-329,共4页Chinese Journal of Construction Machinery

摘　　要：压水堆核电厂反应堆堆内构件联接件在高温、辐照环境中工作,承受由水流、地震等引起的动态载荷,而其中的流致振动往往会导致联接件的松动、脱落,进而影响堆内构件的完整性,因而联接件的防松性能是一个非常值得关注的问题.针对设计寿期为40年的某压水堆核电厂堆内构件联接件的防松结构,阐述根据堆内构件模型流致振动试验结果,确定等效振动考核试验参数的方法,并对联接件的防松性能进行了振动加速考核试验,得到了对实际工程有参考意义的结论.Under circumstances of high temperature and radiation,the fasteners of Pressurized Water Reactor（PWR） internals suffer from such dynamical loadings as water-flows and earthquakes.In particular,the flow-produced vibrations result in fastener looseness and detachment so as to damage the structural integrality.As such,the anti-looseness performance of fasteners deserves extensive concerns.Pertaining to the anti-looseness structures for fasteners of a specific PWR internals with 40-year design life-cycle,the flow-produced vibrations are tested through internal modeling.Accordingly,an equivalent vibratory examination is conducted to attain testing parameters.Furthermore,the vibratory acceleration is used to examine the anti-looseness performance.Thereafter,this approach sets a reference for engineering applications.

关 键 词：堆内构件联接件 防松结构 等效振动考核 

分 类 号：TU352[建筑科学—结构工程]