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

Journal Article · · npj Materials Degradation
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 simulation on the research progress of the CISCC. The numerical models emphasizing the residual stress, susceptible microstructure, and corrosive environment are summarized individually. Meanwhile, the simulation studies on the role of hydrogen-assisted cracking are reviewed. Finally, a multi-physical numerical model, which combines the different fields is proposed based on our recent investigation.

Research Organization:
Colorado School of Mines, Golden, CO (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
NE0008442
OSTI ID:
1850486
Journal Information:
npj Materials Degradation, Journal Name: npj Materials Degradation Journal Issue: 1 Vol. 5; ISSN 2397-2106
Publisher:
Springer
Country of Publication:
United States
Language:
English

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