压力容器2018，Vol.35Issue(2)：24-28,5.DOI:10.3969/j.issn.1001-4837.2018.02.004
反应堆压力容器主螺栓螺纹疲劳分析方法
Fatigue Analysis for Screw Threads of Reactor Pressure Vessel Stud
陈涛 1刘攀 2徐晓1
作者信息
- 1. 深圳中广核工程设计有限公司,广东深圳 518172
- 2. 核电安全监控技术与装备国家重点实验室,广东深圳 518172
- 折叠
摘要
Abstract
Screw threads on studs connecting head and vessel flange of reactor pressure vessel is one of the representative regions with small margin of fatigue analysis among nuclear island primary equipment.Con-sidering structure of the stud and the hole on the head vessel,comparisons are made to optimize fatigue a-nalysis method of the screw threads in the aspect of simplifying method of the thread model,way of getting of the stresses,grouping and combining of transient loads of temperature and pressure,choosing and using of fatigue strength reduction factor Kf,ect.Conclusions about influences of all the above factors are summed up,and an effective method to maximize margins of fatigue analysis for screw threads are given. This method can be used for the design of reactor pressure vessel stud.关键词
反应堆压力容器/螺栓螺纹/疲劳分析/疲劳强度减弱系数Key words
reactor pressure vessel/screw thread of stud/fatigue analysis/fatigue strength reduction factor分类
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陈涛,刘攀,徐晓..反应堆压力容器主螺栓螺纹疲劳分析方法[J].压力容器,2018,35(2):24-28,5.
