63 citations
2 papers
cond-mat.mtrl-sci2018★ 15 cited
Void growth and coalescence in irradiated copper under deformation
P. O. Barrioz, J. Hure, B. Tanguy
A decrease of fracture toughness of irradiated materials is usually observed, as reported for austenitic stainless steels in Light Water Reactors (LWRs) or copper alloys for fusion…
cond-mat.mtrl-sci2016★ 63 cited
Intergranular stress distributions in polycrystalline aggregates of irradiated stainless steel
J. Hure, S. El Shawish, L. Cizelj +1
In order to predict InterGranular Stress Corrosion Cracking (IGSCC) of post-irradiated austenitic stainless steel in Light Water Reactor (LWR) environment, reliable predictions of…