A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions
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/10.1007/978-3-319-67244-1_28
Publication URI: http://dx.doi.org/10.1007/978-3-319-67244-1_28
Type: Book Chapter
Book Title: Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (2018)
Page Reference: 439-454
ISSN: 1436-3798