Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding
Author:
Funder
Board of Research in Nuclear Sciences
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference55 articles.
1. Rupture behaviour of nuclear fuel cladding during loss-of-coolant accident;Suman;Nucl. Eng. Des.,2016
2. Creep behavior of hydrogenated zirconium alloys;Sarkar;J. Mater. Eng. Perform.,2014
3. Corrosion of zirconium alloys used for nuclear fuel cladding;Motta;Annu. Rev. Mater. Res.,2015
4. Parameter study on the influence of prepressurization on PWR fuel rod behavior during normal operation and hypothetical LOCAs;Brzoska;Nucl. Technol.,1979
5. Effects of rod pre-pressurization on light water reactor fuel behavior during reactivity initiated accident conditions;Saito;J. Nucl. Sci. Technol.,1982
Cited by 20 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. The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4;Journal of Nuclear Materials;2024-11
2. Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing;Materials Science and Engineering: A;2024-11
3. Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube;Journal of Nuclear Materials;2024-08
4. Thermal Creep in a Pre-Hydrided Zr1% Nb Nuclear Fuel Cladding Tube;2024
5. The Influence of Hydrogen on the Creep Behavior of Zircaloy-4 Cladding in Low Burnup Regime;2024
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