Investigation of stress corrosion crack propagation characteristics and life prediction for thick-walled double U-groove pipe welds in PWR steam generator

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Baoyin Zhu , Zheng He , Lu Zhang , Shuitao Gu , Xiao Jin , Dungui Zuo , Gongye Zhang
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引用次数: 0

Abstract

Stress corrosion cracking (SCC) is a critical concern in evaluating the structural integrity of pressurized water reactor (PWR) primary pressure boundaries. Material mismatch and welding-induced residual stresses introduce significant challenges in predicting crack propagation paths and service-induced defect lifetimes. This study examines the influence of welding residual stress on SCC in a thick-walled double U-groove pipe dissimilar steel welded joint of a PWR steam generator (SG), and assesses the propagation life of SCC from an engineering standpoint. First, the distribution and stress state of residual stresses in complex SG dissimilar steel joints were analyzed using the two-way thermal coupling finite element method to establish initial stress boundary conditions for simulating SCC propagation influenced by residual stresses. Next, the extended finite element method combined with the maximum principal stress criterion was employed to investigate the propagation direction and path of cracks originating from various initial positions due to welding residual stresses. Concurrently, the J-integral method was used to calculate the stress intensity factors of cracks at different depths along the propagation path. Finally, based on the modified Shoji model, the relationship between the stress intensity factor and SCC propagation rate was examined, allowing for predictions of crack propagation rates and service life for SCC with varying initial defects.
压水堆蒸汽发生器厚壁双u型槽管焊缝应力腐蚀裂纹扩展特性及寿命预测研究
应力腐蚀开裂(SCC)是评价压水堆主压力边界结构完整性的关键问题。材料失配和焊接引起的残余应力对裂纹扩展路径和使用缺陷寿命的预测提出了重大挑战。研究了压水反应堆蒸汽发生器(SG)厚壁双u型槽管异种钢焊接接头中焊接残余应力对SCC的影响,并从工程角度评估了SCC的传播寿命。首先,采用双向热耦合有限元法分析SG异种钢复杂接头中残余应力的分布和应力状态,建立模拟残余应力影响下SCC扩展的初始应力边界条件;其次,采用扩展有限元法结合最大主应力准则,研究了焊接残余应力在不同初始位置产生裂纹的扩展方向和路径。同时,采用j积分法计算了裂纹沿扩展路径不同深度的应力强度因子。最后,基于改进的Shoji模型,研究了应力强度因子与SCC扩展速率之间的关系,从而可以预测具有不同初始缺陷的SCC的裂纹扩展速率和使用寿命。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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