Experimental investigation and characterization of the vibration fatigue S-N curve for small-diameter 316L stainless steel butt-welded pipes

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ning Li , Hongbo Gao , Lei Lin , Pin Li , Shuai Zhou , Han Liu , Changning Li , Decheng Xu , Yin Liu , Zhilin Chen
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引用次数: 0

Abstract

Vibration fatigue in small-diameter pipes (SDP) represents a key failure mode in industrial pipeline systems, with butt-welded joints constituting the critical weak links. This study addresses the lack of specific component-level vibration fatigue data for 316L stainless steel butt-welded SDP and the insufficient accuracy of traditional evaluation methods (based on base material data with generic Fatigue Strength Reduction Factors), aiming to experimentally obtain and characterize the vibration fatigue S-N curves for these components.The experimental methodology employed an electromagnetic vibration table to conduct component-level resonance bending fatigue tests on 316L butt-welded pipe specimens with an outer diameter (OD) of 16 mm and a wall thickness of 3 mm. Constant amplitude loading was applied at the first-order bending resonance frequency of the specimens (approximately 58 Hz), with stress amplitude monitored and controlled via strain gauges. Failure detection was implemented through gas leakage monitoring. Residual stresses after welding and dynamic stress concentration factors (SCF) were measured using X-ray diffraction (XRD) and digital image correlation (DIC) techniques, respectively. The results successfully established the component-level S-N curve for the joint, determining the median fatigue strength at 107 cycles (162.5 MPa) and the lower limit of design fatigue strength (148.7 MPa). All failures initiated at the weld toe, where SCF values ranged from 1.26 to 1.47. Significant residual compressive stresses were identified on the outer surface of the weld, exhibiting a negative correlation with weld reinforcement height. Under medium and high stress conditions, fatigue life decreased with increasing reinforcement height. Compared to ASME standard reference data, the component-level S-N curves developed in this study exhibited superior fatigue resistance in the medium–high cycle and fatigue limit regions. The component-level S-N curves obtained in this research incorporate the influences of actual weld geometry, residual stress distribution, and microstructural characteristics, providing a more accurate and reliable fatigue assessment basis for 316L butt-welded small-diameter pipes. These findings support optimized design approaches and provide a reference for evaluating the conservatism of standard assessment methods, which has significant implications for improving the safety and reliability of pipeline systems.
小直径316L不锈钢对接焊管振动疲劳S-N曲线的试验研究与表征
小口径管道振动疲劳是工业管道系统的一种重要失效模式,对接接头是管道系统的关键薄弱环节。针对316L不锈钢对接焊SDP缺乏特定构件级振动疲劳数据以及传统评价方法(基于通用疲劳强度折减系数的基材数据)准确性不足的问题,通过实验获得并表征这些构件的振动疲劳S-N曲线。实验方法采用电磁振动台对外径为16mm、壁厚为3mm的316L对接焊管试件进行构件级共振弯曲疲劳试验。在试件的一阶弯曲共振频率(约58 Hz)下施加恒幅加载,应力幅值通过应变片监测和控制。通过气体泄漏监测实现故障检测。采用x射线衍射(XRD)和数字图像相关(DIC)技术分别测量焊接后残余应力和动态应力集中系数(SCF)。结果成功建立了接头的部件级S-N曲线,确定了107次循环时接头的疲劳强度中值(162.5 MPa)和设计疲劳强度下限(148.7 MPa)。所有失效都始于焊接趾部,SCF值在1.26 ~ 1.47之间。焊缝外表面残余压应力显著,与焊缝钢筋高度呈负相关。在中、高应力条件下,随着钢筋高度的增加,疲劳寿命降低。与ASME标准参考数据相比,本研究开发的构件级S-N曲线在中-高周和疲劳极限区域具有更好的抗疲劳性能。本研究获得的构件级S-N曲线综合考虑了实际焊缝几何形状、残余应力分布和微观组织特征的影响,为316L对接焊小直径管的疲劳评估提供了更加准确可靠的依据。研究结果为优化设计方法提供了依据,为评价标准评价方法的稳健性提供了参考,对提高管道系统的安全性和可靠性具有重要意义。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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