Very low cycle fatigue behavior of SA508 Gr. 1a LAS and SA312 TP316 SS in displacement-control mode cyclic loads

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology Pub Date : 2025-09-25 DOI:10.1016/j.net.2025.103938

Sang Eon Kim , Jin Weon Kim , Jong-Sung Kim

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引用次数: 0

Abstract

This study investigates the deformation and failure behavior of two nuclear structural materials—SA508 Gr.1a low-alloy steel (LAS) and SA312 TP316 stainless steel (SS)—in the very low cycle fatigue (VLCF) regime. Displacement-controlled cyclic tests were performed on notched round-bar specimens with two notch radii (R1.5 and R6.0), spanning both low cycle fatigue (LCF) and VLCF regimes. All tests were conducted at room temperature (RT) under quasi-static loading.

In the VLCF regime, SA312 TP316 SS exhibited pronounced cyclic hardening that intensified with smaller notch radius and larger displacement amplitude, whereas SA508 Gr.1a LAS showed negligible hardening with little sensitivity to notch radius. Even in the VLCF regime, no significant reduction in fatigue life was observed when the fatigue life exceeded 10 cycles for either material; the fatigue life could be appropriately described by the Coffin–Manson relationship established from the LCF regime. Regardless of the material type or notch radius, all specimens in the VLCF regime with more than 10 cycles failed due to surface cracking, which is a typical failure mode in the LCF regime.

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SA508 Gr. 1a LAS和SA312 TP316 SS在位移控制模式下的极低周疲劳行为

本文研究了两种核结构材料——sa508 Gr.1a低合金钢（LAS）和SA312 TP316不锈钢（SS）在极低周疲劳（VLCF）状态下的变形和破坏行为。位移控制循环试验采用两种缺口半径（R1.5和R6.0）的缺口圆杆试件，跨越低周疲劳（LCF）和VLCF状态。所有试验均在室温下准静态加载下进行。在VLCF条件下，SA312 TP316 SS表现出明显的循环硬化，并且随着缺口半径的减小和位移幅度的增大而加剧，而SA508 Gr.1a LAS的硬化可以忽略，对缺口半径的敏感性很小。即使在VLCF条件下，当两种材料的疲劳寿命超过10个循环时，也没有观察到疲劳寿命的显著降低；疲劳寿命可以用LCF建立的Coffin-Manson关系来描述。无论材料类型或缺口半径如何，循环次数超过10次的试样均因表面开裂而失效，这是典型的LCF破坏模式。

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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来源期刊

Nuclear Engineering and Technology 工程技术-核科学技术

CiteScore

4.80

自引率

7.40%

发文量

431

审稿时长

3.5 months

期刊介绍： Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development