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考虑应力松弛和辐照影响的堆内构件压紧弹簧疲劳可靠性评估方法 被引量:2

Fatigue Reliability Evaluation Method for Hold Down Spring of Reactor Vessel Internals Considering Stress Relaxation and Irradiation
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摘要 针对反应堆堆内构件压紧弹簧疲劳失效模式,在考虑应力松弛和辐照影响的条件下基于仿真方法开展可靠性评估。首先结合疲劳模型和平均应力松弛Landgraf模型,考虑辐照对疲劳参数的影响,构建了压紧弹簧疲劳寿命模型。在压紧弹簧疲劳寿命模型基础上,根据广义应力-强度干涉模型定义压紧弹簧可靠度并开展灵敏度分析。以非能动压水堆AP1000压紧弹簧为例进行案例分析,在95%置信度水平下,分别计算了可靠度为95%和50%时对应的疲劳寿命。结果表明,若不考虑应力松弛,压紧弹簧总疲劳寿命下降88.3%;从经济性角度考虑寿命预测结果较为保守。通过灵敏度分析发现对可靠度影响较大的设计变量是弹性模量和疲劳强度系数,在一定可靠度下可以通过调整设计变量对压紧弹簧的疲劳可靠性评估进行优化。 For the fatigue failure modes of the holddown spring of reactor internals,the reliability evaluation was carried out based on the simulation method under the condition of considering the stress relaxation and the influence of radiation.Firstly,combining the fatigue model and the stress relaxation Landgraf model,considering the influence of irradiation on the fatigue parameters,the fatigue life model of the holddown spring was established.Based on the holddown spring fatigue life model,the reliability of holddown spring was defined according to the generalized stress-strength interference model and the sensitivity analysis was carried out.Taking the holddown spring of AP1000 passive pressurized water reactor as an example,the fatigue life with a reliability of 95%and 50%at 95%confidence level were calculated.The results show that the total fatigue life of the holddown spring decreases by 88.3%without considering the stress relaxation,and the prediction results are conservative from the perspective of economy.The results of sensitivity analysis show that the elastic modulus and fatigue strength coefficient have great influence on reliability.The holddown spring can be optimized by adjusting the design variables under certain reliability requirements.
作者 张翼 李燕 孙博 曹奇锋 潘俊林 杨西 杨德真 任羿 Zhang Yi;Li Yan;Sun Bo;Cao Qifeng;Pan Junlin;Yang Xi;Yang Dezhen;Ren Yi(Nuclear Power Institute of China,Chengdu,610213,China;School of Reliability and Systems Engineering,Beihang University,Beijing,100191,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2021年第6期141-147,共7页 Nuclear Power Engineering
关键词 压紧弹簧 可靠性 疲劳 应力松弛 辐照 反应堆结构 Holddown spring Reliability Fatigue Stress relaxation Irradiation Reactor structure
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