Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7963000 | Journal of Nuclear Materials | 2018 | 26 Pages |
Abstract
Understanding the corrosion behaviour of zirconium alloys is essential in providing cost effective and safe operation of nuclear power plant. Long-term corrosion testing of Zircaloy-4 and Zircaloy-2 in 350â¯Â°C pressurised water is presented with detailed analysis of the oxide's development. The correlation of the corrosion and analytical data provides a detailed understanding regarding the point at which different microstructural features, such as cracking, occur during the cyclic corrosion process. The results from this work show that the large scale cracking, which is often associated with the cyclic transitions, evolve following, rather than prior to, the onset in rapid corrosion.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Mhairi Gass, Mark Fenwick, Helen Hulme, Michael Waters, Paul Binks, Alexandra Panteli, Mark Chatterton, Victoria Allen, Aidan Cole-Baker,