防断组件及其支承柱高周疲劳分析  

High cycle fatigue analysis of vortex suppression plate and secondary core support structures

作　　者：薛国宏[1] 李源[1] 赵飞云[1] 冯少东[1] 于浩[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核技术》2013年第4期200-204,共5页Nuclear Techniques

摘　　要：反应堆堆内构件是反应堆冷却剂系统中的重要设备,其设计结构要求在全寿期内保持高度可靠性。在国内外核电厂运行过程中,曾发生堆内构件因流致振动而出现故障和损坏事件,直接影响了反应堆的安全运行和经济效益。本文以堆内构件防断组件及其支承柱(SCSS)为研究对象,研究其在流致振动载荷和泵致振动载荷下的动态响应,并对结构进行谱分析和谐响应分析。最后根据ASME锅炉及压力容器规范对防断组件及其支承柱各部件进行高周疲劳评定,计算结果表明各部件交变应力强度满足规范限值的要求。Background： Reactor internals are important equipments in the reactor coolant system, its structure design needs high reliability in the entire lifetime. Reactor internals have occurred breakdown and the damage event due to flow induced vibrations in the domestic and foreign nuclear power plants, which make immediate influence on reactor safe operation and economic efficiency. Purpose： In this work, the dynamic response of reactor internals-vortex suppression plate and secondary core support structure （SCSS） under the loading from pump induced vibrations and flow induced vibrations are studied. Methods： Based on the finite element model of SCSS, Spectrum analysis and the harmonious analysis are performed, in order to get the response of the structure under flow induced vibrations. Then, the high fatigue of the structure is assessed according to the ASME B＆PV Code. Results： The results indicate that alternate stresses of all the components satisfy the limiting value in the correlative requirements. Conclusions： The structure of SCSS could bear the vibration induced from the flow and the pump, and the method used in this article provides the reference for other reactor internals structure analysis like this.

关 键 词：堆内构件 流致振动 泵致振动 高周疲劳 

分 类 号：TL351[核科学技术—核技术及应用] TB12[理学—工程力学]