Comments on “aqueous corrosion of the Zircaloys at low temperatures”
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Aqueous corrosion of the zircaloys at low temperatures
2. Low temperature (< 300 °c) oxidation of Zircaloy-2 in water
3. The kinetics and mechanism of the oxidation of zircaloy-2 at 350–500 °C
4. Metallurgy of Zirconium;Thomas,1955
Cited by 7 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. Effect of Sn on Corrosion Mechanisms in Advanced Zr-Cladding for Pressurised Water Reactors;Zirconium in the Nuclear Industry: 17th Volume;2014-06-19
2. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr–Sn–Nb alloys;Acta Materialia;2013-06
3. Autoclave study of zirconium alloys with and without hydride rim;Corrosion Engineering, Science and Technology;2012-11
4. The oxidation of ordered Zr3Al;Metallurgical Transactions A;1980-05
5. Oxidation of Zirconium and its Alloys;Advances in Corrosion Science and Technology;1976
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