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A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions

First Author: Shen Z

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