The effects of strain amplitude and temperature on kinematic hardening parameters for low cycle fatigue of AISI316L stainless steel

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-06-16 DOI:10.1016/j.nucengdes.2025.114221

Sushant Bhalchandra Pate , Gintautas Dundulis , Stephan Courtin , Jean-Christophe Le Roux

引用次数: 0

Abstract

To perform a numerical simulation of low-cycle fatigue behaviour it is very important to model the elastoplastic behaviour of the material and for this, the proper estimation of the kinematic hardening parameters is a very critical part. The estimation of this kinematic hardening parameter is a very complex and time-consuming process. In the presented work, an experimental and numerical investigation of the low cycle fatigue behaviour of AISI316L stainless steel was carried out on the solid and hollow specimens with different strain amplitudes and temperatures. The simulation results were compared with the experimental data, and the agreement of these results was acceptable. On the basis of the results, preliminary equations for the estimation of kinematic hardening parameters are proposed, and the estimated parameters through these equations gave simulation results to the experimental results.

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应变幅值和温度对AISI316L不锈钢低周疲劳运动硬化参数的影响

为了对材料的低周疲劳行为进行数值模拟，对材料的弹塑性行为进行建模是非常重要的，而对运动硬化参数的正确估计是非常关键的一环。这种运动硬化参数的估计是一个非常复杂和耗时的过程。本文对AISI316L不锈钢在不同应变幅值和温度下的实心和空心试样的低周疲劳行为进行了实验和数值研究。将仿真结果与实验数据进行了比较，结果吻合较好。在此基础上，提出了预估运动硬化参数的初步方程，并将预估参数与实验结果进行了仿真。

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 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.