Fatigue behavior and lifetime assessment of an austenitic stainless steel in the VHCF regime at ambient and elevated temperatures

Author:

Schopf Tim1,Weihe Stefan1,Daniel Tobias2,Smaga Marek2,Beck Tilmann2

Affiliation:

1. Materials Testing Institute (MPA) University of Stuttgart Stuttgart Germany

2. Institute of Materials Science and Engineering (WKK) University of Kaiserslautern Kaiserslautern Germany

Abstract

AbstractWhile the LCF behavior of austenitic steels used in nuclear power plants is already well investigated, the VHCF regime has not been characterized in detail so far. For this, fatigue tests on the metastable austenitic steel AISI 347/1.4550 were performed with a servo‐hydraulic testing system at test frequencies up to 980 Hz and with an ultrasonic fatigue testing system at a test frequency of 20,000 Hz. To compare these test results to the ASME standard fatigue curve (total strain amplitude vs. load cycles to failure), a fictitious‐elastic and an elastically plastic assessment method was used. The elaborated elastic–plastic assessment method generates good results, while a purely elastic assessment in the VHCF regime, commonly used in literature, leads to significantly nonconservative results. Moreover, phase transformation from metastable austenite into stable α′‐martensite can take place, and no specimen failure occurs in the VHCF regime. Consequently, for this material, a real endurance limit exists.

Publisher

Wiley

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference29 articles.

1. ChopraOK ShackWJ.Effect of LWR Coolant Environments on the fatigue life of reactor materials.Final Report NUREG/CR‐6909 Rev. 1 U.S. Nuclear Regulatory Commission 2018.

2. KTA 3201: components of the reactor coolant pressure boundary of light water reactors. Part 2: design and analysis German Nuclear Safety Standard Ed.2017.

3. KTA 3204: reactor pressure vessel internals German Nuclear Safety Standard Ed. 2017‐11 p. 39.

4. ASME Boiler & Pressure Vessel Code.Section III division 1 – subsection NB: class 1 components rules for construction of nuclear power plant components The American Society of Mechanical Engineers 2019.

5. Fatigue Testing at 1000Hz Testing Frequency

Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3