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

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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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
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spelling doaj-9fd1cd83596a4e96ba5cb81de0badcae2021-05-30T11:27:30ZengNature Publishing Groupnpj Materials Degradation2397-21062021-05-015111410.1038/s41529-021-00174-5Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canistersXin Wu0Fengwen Mu1School of Chemical Engineering and Technology, Sun Yat-Sen University, ZhuhaiHigh-Frequency High-Voltage Device and Integrated Circuits R&D Center, Institute of Microelectronics of Chinese Academy of SciencesAbstract 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.https://doi.org/10.1038/s41529-021-00174-5
collection DOAJ
language English
format Article
sources DOAJ
author Xin Wu
Fengwen Mu
spellingShingle Xin Wu
Fengwen Mu
Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
npj Materials Degradation
author_facet Xin Wu
Fengwen Mu
author_sort Xin Wu
title Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
title_short Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
title_full Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
title_fullStr Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
title_full_unstemmed Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
title_sort development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
publisher Nature Publishing Group
series npj Materials Degradation
issn 2397-2106
publishDate 2021-05-01
description 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.
url https://doi.org/10.1038/s41529-021-00174-5
work_keys_str_mv AT xinwu developmentofanumericalmodelforsimulatingstresscorrosioncrackinginspentnuclearfuelcanisters
AT fengwenmu developmentofanumericalmodelforsimulatingstresscorrosioncrackinginspentnuclearfuelcanisters
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