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...

Descripción completa

Guardado en:

Detalles Bibliográficos
Autores principales:	Xin Wu, Fengwen Mu
Formato:	article
Lenguaje:	EN
Publicado:	Nature Portfolio 2021
Materias:	Materials of engineering and construction. Mechanics of materials TA401-492
Acceso en línea:	https://doaj.org/article/9fd1cd83596a4e96ba5cb81de0badcae
Etiquetas:	Agregar Etiqueta Sin Etiquetas, Sea el primero en etiquetar este registro!

id	oai:doaj.org-article:9fd1cd83596a4e96ba5cb81de0badcae
record_format	dspace
spelling	oai:doaj.org-article:9fd1cd83596a4e96ba5cb81de0badcae2021-12-02T15:00:55ZDevelopment of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters10.1038/s41529-021-00174-52397-2106https://doaj.org/article/9fd1cd83596a4e96ba5cb81de0badcae2021-05-01T00:00:00Zhttps://doi.org/10.1038/s41529-021-00174-5https://doaj.org/toc/2397-2106Abstract 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.Xin WuFengwen MuNature PortfolioarticleMaterials of engineering and construction. Mechanics of materialsTA401-492ENnpj Materials Degradation, Vol 5, Iss 1, Pp 1-14 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Materials of engineering and construction. Mechanics of materials TA401-492
spellingShingle	Materials of engineering and construction. Mechanics of materials TA401-492 Xin Wu Fengwen Mu Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
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.
format	article
author	Xin Wu Fengwen Mu
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 Portfolio
publishDate	2021
url	https://doaj.org/article/9fd1cd83596a4e96ba5cb81de0badcae
work_keys_str_mv	AT xinwu developmentofanumericalmodelforsimulatingstresscorrosioncrackinginspentnuclearfuelcanisters AT fengwenmu developmentofanumericalmodelforsimulatingstresscorrosioncrackinginspentnuclearfuelcanisters
_version_	1718389155048718336

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

Ejemplares similares