Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters

Abstract Prediction and detection of the chloride-induced stress corrosion cracking (CISCC) in Type 304 stainless steel spent nuclear fuel canisters are vital for the lifetime extension of dry storage canisters. This paper conducts a critical review that focuses on the numerical modeling and simulat...

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Bibliographic Details
Main Authors: Xin Wu, Fengwen Mu
Format: Article
Language:English
Published: Nature Publishing Group 2021-05-01
Series:npj Materials Degradation
Online Access:https://doi.org/10.1038/s41529-021-00174-5