文献类型：期刊文献

中文题名：弯曲载荷对含环向贯穿缺陷的核电厂蒸汽发生器传热管爆破压力影响研究

英文题名：Research on the Influence of Bending Load on the Burst Pressure of Steam Generator Heat Tubes with Circumferential Through-Wall Defects in Nuclear Power Plants

作者：杨成[1];王建军[1];黄淞[2];惠虎[2];聂希[1];谭晓敏[1]

机构：[1]核电运行研究(上海)有限公司,上海200120;[2]华东理工大学机械与动力工程学院,上海200237

年份：2026

卷号：63

期号：2

起止页码：1

中文期刊名：化工设备与管道

外文期刊名：Process Equipment & Piping

收录：;北大核心:【北大核心2023】；

语种：中文

中文关键词：蒸汽发生器传热管;弯曲载荷;爆破压力;环向裂纹;净截面垮塌

外文关键词：steam generator heat tube;bending load;burst pressure;circumferential crack;net section collapse

摘要：事故工况下的弯曲载荷对含环向贯穿缺陷的核电蒸汽发生器传热管爆破压力存在影响。针对压水堆核电厂典型蒸汽发生器U型传热管,建立了传热管弯曲载荷和内压组合载荷下的爆破压力有限元计算模型,采用塑性极限分析方法建立了弯曲与内压组合载荷下的传热管爆破压力与临界弯曲应力计算方法,并与西屋开展的公开文献爆破试验结果进行了对比分析。结果表明,文章的方法是保守的,弯曲应力和裂纹环向角度的增大均导致传热管爆破压力降低,当环向角度大于50°时,弯曲应力可导致爆破压力低于传热管结构完整性限值,同时给出了爆破临界弯曲应力和裂纹环向角度的具体关系,可为核电厂Inconel690合金蒸汽发生器传热管结构完整性评估提供参考。
The bending load under accident conditions poses a challenge to the burst pressure of heat tubes in nuclear power steam generators with circumferential through-Wall defects.A finite element calculation model was established for the burst pressure of a typical U-bend heat tube in steam generators under combination bending load and internal pressure load.A method for calculating the burst pressure and critical bending stress of heat tubes under combined bending and internal pressure loads was established using plastic limit analysis and comparative analysis was carried out with the burst test results from public literature conducted by Westinghouse.The results show that the method proposed in this article is conservative.Both the increase of bending stress and the circumferential angle of the crack lead to the decrease of the burst pressure of the heat transfer tube.When the circumferential angle is greater than 50°,the bending stress will cause the burst pressure to be lower than the structural integrity limit of the heat tubes,and the specific relationship between the critical bending stress for burst and the circumferential angle of the crack is given which could provide reference for the structural integrity assessment of Inconel 690 alloy steam generator heat tubes in nuclear power plants.