Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels
Author:
Affiliation:
1. Westinghouse Hanford Company, Richland, Washington 99352
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT73-A15876
Reference35 articles.
1. Fatigue-crack propagation behavior of type 304 stainless steel at elevated temperatures
2. Fatigue Crack Growth in Type 316 Stainless Steel at High Temperature
3. Fatigue-Crack Growth in 20% Cold-Worked Type 316 Stainless Steel at Elevated Temperatures
Cited by 17 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
1. On load-following operations of small modular reactors;Progress in Nuclear Energy;2024-08
2. Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials;Journal of Pressure Vessel Technology;2017-10-06
3. A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels;Journal of Nuclear Materials;2011-02
4. Fatigue behavior of 20% cold-worked 316 stainless steel under in situ irradiation with 17 MeV protons at 60 °C;Journal of Nuclear Materials;2002-04
5. Influence of radiation damage on the cyclic crack resistance of austenitic steels and alloys (review);Strength of Materials;1991-07
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