安全端异种金属焊接接头应力腐蚀裂纹尖端裂纹生长驱动力综述

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zheng Wang , Yuxuan Xue , Rongxin Wang , Jun Wu , Yubiao Zhang , He Xue
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引用次数: 0

摘要

核电站(NPP)的焊接结构材料在长期的高温高压水环境中容易发生以应力腐蚀开裂(SCC)为代表的环境辅助开裂(EAC),对核电站的安全构成重大威胁。本研究旨在对核电站安全端异种金属焊接接头(DMWJ)中 SCC 尖端裂纹生长驱动力进行深入探讨。首先,介绍了 SCC 的背景、重要性和研究现状。其次,对 SCC 的起始和生长阶段进行了综述和分析,重点介绍了实验方法、裂纹生长速率预测模型、裂纹尖端力学状态和影响因素,阐明了当前实验和理论研究的主要成果和挑战。最后,提出了减缓裂纹尖端驱动力的方法,并从力学角度深入分析了裂纹生长驱动力与裂纹生长阻力之间的关系,强调了未来的研究趋势。本综述为解决核电站一次回路焊接结构材料中的 SCC 问题提供了理论参考和技术支持。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Review on crack growth driving force at the tip of stress corrosion cracking in the safe end dissimilar metal welded joint
The welded structural materials of nuclear power plants (NPPs) are susceptible to environmentally-assisted cracking (EAC), represented by stress corrosion cracking (SCC), in prolonged high-temperature and high-pressure water environments, posing a significant threat to plant safety. This study aims to provide a critical review for the crack growth driving force at the tip of SCC in the safe end dissimilar metal welded joint (DMWJ) of NPPs. Firstly, SCC’s background, importance, and current research status are introduced. Secondly, a review and analysis are conducted on SCC’s initiation and growth stages, focusing on experimental methods, predictive models of crack growth rate, crack tip mechanical states, and influencing factors, clarifying the main achievements and challenges in current experimental and theoretical research. Finally, a method to mitigate crack tip driving force is proposed, followed by an in-depth analysis from a mechanical perspective on the relationship between crack growth driving force and crack growth resistance, highlighting future research trends. This review provides theoretical references and technical support for addressing the issue of SCC in welded structural materials of NPP primary circuit.
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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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