Effect of interface undulation on the high temperature oxidation behaviors of grit-blasted and coated zircaloy in pressurized water
Creators
- 1. School of Materials Science and Engineering, Henan University of Science and Technology, Luoyang 471023, Henan (China)
- 2. Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 519082, Guangdong (China)
- 3. State Key Laboratory of Solid Lubrication, Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences, Lanzhou 730000 (China)
- 4. Institute of Fuel Cells, School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240 (China)
Description
Highlights: • The grit-blasted and coated zircaloys present higher corrosion rate than the as-received substrate during early stage. • Interface undulation can result in redistribution of the oxide growth stress of zircaloy. • Local stress concentration induces initiation of cracks and therefore increases the corrosion rate of zircaloy. Effect of interface undulation on the high-temperature oxidation behaviors of grit-blasted and coated zircaloys in pressurized water was investigated. The grit-blasted and the coated zircaloy substrates present significantly higher corrosion rate than the as-received flat substrate during the early stage of exposure. Numerical analysis suggests the interface undulation results in redistribution of the oxide growth stress of zircaloy, as well as varying the local stress concentration, which induces initiation of cracks and therefore increases the corrosion rate of zircaloy. Propagation of cracks along the interface drives delamination of the protective coating. Results of this work not only promote understanding of the coating/substrate interface evolution in high-temperature pressurized water, but also provide a guide to design corrosion-resistant zirconium alloys and/or coatings for fuel cladding.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.corsci.2021.109839Additional details
Identifiers
- DOI
- 10.1016/j.corsci.2021.109839;
- PII
- S0010938X21006053;
Publishing Information
- Journal Title
- Corrosion Science
- Journal Volume
- 192
- Journal Page Range
- vp.
- ISSN
- 0010-938X
- CODEN
- CRRSAA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54016686
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CLADDING; CONCENTRATION RATIO; CORROSION; CORROSION RESISTANCE; CRACKS; EXPLOSIVE FRACTURING; NUCLEAR FUELS; NUMERICAL ANALYSIS; OXIDATION; OXIDES; PROTECTIVE COATINGS; STRESSES; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; COATINGS; DEPOSITION; DIMENSIONLESS NUMBERS; ENERGY SOURCES; FRACTURING; FUELS; MATERIALS; MATHEMATICS; OXYGEN COMPOUNDS; REACTOR MATERIALS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier Ltd. All rights reserved.