详细信息

核电部件屈曲设计方法的对比分析与案例研究    

Comparative Analysis and Case Study on Buckling Design Methods for Components in Nuclear Power Plants

文献类型:期刊文献

中文题名:核电部件屈曲设计方法的对比分析与案例研究

英文题名:Comparative Analysis and Case Study on Buckling Design Methods for Components in Nuclear Power Plants

作者:刘芳[1];宫建国[1];黑宝平[2];高付海[2];轩福贞[1]

机构:[1]华东理工大学机械与动力工程学院,上海200237;[2]中国原子能科学研究院,北京102413

年份:2019

卷号:36

期号:6

起止页码:18

中文期刊名:压力容器

外文期刊名:Pressure Vessel Technology

收录:CSTPCD;;北大核心:【北大核心2017】;

基金:国家重点研发计划项目(2016YFC0801905);国家自然科学基金项目(51605165)

语种:中文

中文关键词:瞬时屈曲;蠕变屈曲;ASME规范;RCC-MRx标准

外文关键词:instantaneous buckling;creep buckling;ASME code;RCC-MRxstandard

摘要:屈曲是快堆关键部件的重要失效模式,涉及地震载荷下的反应堆主容器、轴压载荷下的泵和换热器支撑筒等部件。为保证反应堆安全可靠地运行,相关部件的屈曲设计至关重要。针对快堆瞬时屈曲和蠕变屈曲失效模式,介绍了ASME规范和RCC-MRx标准中的屈曲设计方法,分析了不同设计方法的差异。最后以轴压载荷下的圆柱壳为例,开展了基于ASME规范和RCC-MRx标准中屈曲设计方法的应用案例研究。
Buckling is a main failure mode of some critical components in fast reactor,involving main vessel of the reactor under seismic load,support cylinders of pump and heat exchanger under axial load,etc.In order to ensure safe and reliable operation of the reactor, the buckling design of relevant components is of vital importance.In view of the failure modes such as the instantaneous buckling and creep buckling,the buckling design methods in ASME and RCC-MRx codes were introduced and the differences in these design methods were analyzed.Finally,an application case based on buckling design methods in ASME and RCC- MRx was studied by taking an axial compressive cylindrical shell as an example.

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