Microstructure evolution and oxidation behavior of bi-layer CrAl-Mo coated Zircaloy-4 in steam at 1200 °C and 1300 °C
Authors:
- Chaowen ZhuCZChaowen Zhu
- Pengcheng LiPLPengcheng Li
- Chen ChenCCChen Chen
- Junhua TianJTJunhua Tian
- Song ZengSZSong Zeng
- Yan MengYMYan Meng
- Huahai ShenHSHuahai Shen
- Xiaochun HanXHXiaochun Han
- Haibin ZhangHZHaibin Zhang
- 7 September 2022
- journal article
- research article
- Published by Elsevier in Corrosion Science
- Vol. 208
Abstract
No abstract availableKeywords
This publication has 31 references indexed in Scilit:
- Microstructure and Oxidation Behavior of CrAl Laser-Coated Zircaloy-4 AlloyMetals, 2017
- Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel claddingJournal of Nuclear Materials, 2016
- Ti3AlC2 coatings deposited by liquid plasma sprayingSurface and Coatings Technology, 2016
- Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditionsJournal of Nuclear Materials, 2016
- A study of the zirconium alloy protection by Cr3C2–NiCr coating for nuclear reactor applicationSurface and Coatings Technology, 2016
- Cold spray deposition of Ti2AlC coatings for improved nuclear fuel claddingJournal of Nuclear Materials, 2015
- A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environmentCorrosion Science, 2015
- Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposureJournal of Nuclear Materials, 2013
- Current knowledge on core degradation phenomena, a reviewJournal of Nuclear Materials, 1999
- Oxidation of Zircaloy by steamJournal of Nuclear Materials, 1991