Oxidation behaviour of solution-annealed and thermally-treated Alloy 690 in low pressure H2-Steam (2020)
Attributed to:
Understanding the mechanisms controlling low potential stress corrosion cracking in nuclear reactors
funded by
EPSRC
Abstract
No abstract provided
Bibliographic Information
Digital Object Identifier: http://dx.doi.org/10.1016/j.corsci.2020.108514
Publication URI: http://dx.doi.org/10.1016/j.corsci.2020.108514
Type: Journal Article/Review
Parent Publication: Corrosion Science