A micromechanical analysis of swelling-induced embrittlement in neutron-irradiated austenitic stainless steels

Swelling is commonly observed in austenitic stainless steels irradiated at high doses and high temperatures, such as fuel claddings in Fast-Breeder Reactors (FBR), as a consequence of the formation of irradiation-induced nanovoids. Macroscopic embrittlement has been reported above a critical swellin...

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Bibliographic Details
Published in:	Journal of nuclear materials Vol. 565; p. 153732
Main Authors:	Hure, J., Courcelle, A., Turque, I.
Format:	Journal Article
Language:	English
Published:	Amsterdam Elsevier B.V 01-07-2022 Elsevier BV Elsevier
Subjects:	Austenitic stainless steels Austenitic steels Breeder reactors Chemical Sciences Coalescence Constitutive equations Constitutive relationships Corrosion effects Deformation effects Embrittlement Finite element method Fracture mechanics Fuels Heterogeneity High temperature Irradiation Material chemistry Microchemistry Neutron irradiation Phase transitions Porous materials Reactors Spatial heterogeneity Stainless steel Swelling Tensile properties Tensile test Theoretical analysis Irradiation Swelling Austenitic steels Tensile test Porous materials Embrittlement
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