热老化对核电站管道材料力学、疲劳和断裂性能的影响

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-10-11 DOI:10.1016/j.nucengdes.2025.114528

Shabna Shirin , S. Vishnuvardhan , Keerthy M. Simon

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引用次数: 0

摘要

核电厂所用的管道材料长时间暴露在高温下，导致热老化，并改变其机械、疲劳和断裂性能。热老化引起循环热应力，导致裂纹的萌生和扩展，并可能损害管道部件的结构完整性。本文综述了热老化对核电厂不同管道材料的影响，如不锈钢、双相不锈钢、铸造奥氏体不锈钢、铸造不锈钢、ODS铁素体钢和91级钢。研究力学性能有助于评估材料的强度和耐久性，而疲劳和断裂性能对于预测循环载荷下的失效非常重要。了解这些特性对于选择合适的材料、优化维护策略和确保核电站的长期安全至关重要。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Effect of thermal ageing on mechanical, fatigue and fracture properties of nuclear power plant piping materials: a review

Piping materials used in nuclear power plants are exposed to high temperatures for extended periods, leading to thermal ageing and which alters their mechanical, fatigue and fracture properties. Thermal ageing cause cyclic thermal stresses resulting in crack initiation and propagation and can compromise the structural integrity of piping components. This review examines the effect of thermal ageing on different piping materials used in nuclear power plants such as stainless steel, duplex stainless steel, cast austenitic stainless steel, cast stainless steel, ODS ferritic steel and Grade 91 steel. Studying mechanical properties helps to evaluate material strength and durability, while fatigue and fracture properties are important for predicting failure under cyclic loading. Understanding these properties is crucial for selecting suitable material, optimizing maintenance strategies and ensuring the long-term safety of nuclear power plants.

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来源期刊

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.