High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference28 articles.
1. L. Baker, L.C. Just, Studies of Metal-Water Reactions at High Temperatures: III. Experimental and Theoretical Studies of the Zirconium-Water Reaction, ANL-6548, May 1962.
2. J.V. Cathcart, R.E. Pawel, R.A. McKee, R.E. Druschel, G.J. Yurek, J.J. Campbell, S.H. Jury, Zirconium Metal-Water Oxidation Kinetics: IV. Reaction Rate Studies, ORNL/NUREG-17, August 1977.
3. The oxidation behavior of Zircaloy-4 in steam between 600 and 1600°C
4. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions
5. Pseudobinary zircaloy-oxygen phase diagram
Cited by 57 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. Performance analysis of zirconium alloy after long-term cooling after simulated LOCA test;Nuclear Engineering and Design;2024-08
2. High-temperature degradation behavior of PEO-coated ZIRLO alloy in N2 and N2+steam environments at 900 and 1000 °C;Journal of Nuclear Materials;2024-08
3. Investigation on nanoindentation and TOF-SIMS applications in the hydrogen and oxygen absorption behavior of Zr-Sn-Nb alloys;Journal of Alloys and Compounds;2024-08
4. High-performance Cr2AlC MAX phase coatings for ATF application: Interface design and oxidation mechanism;Corrosion Communications;2024-03
5. High-Temperature Degradation Behavior of Peo-Coated Zirlo Alloy in N2 and N2+Steam Environments at 900 and 1000°C;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