63 citations · 130 across the 4 of their papers we have counts for
4 papers
A micromechanical analysis of intergranular stress corrosion cracking of an irradiated austenitic stainless steel
D. Liang, J. Hure, A. Courcelle +2
Irradiation Assisted Stress Corrosion Cracking (IASCC) is a material degradation phenomenon affecting austenitic stainless steels used in nuclear Pressurized Water Reactors (PWR),…
Assessing size effects on the deformation of nanovoids in metallic materials
J. Hure, P. O. Barrioz, B. Tanguy
An experimental methodology is developed to evaluate size effects in nanovoids deformation under macroscopic uniaxial stress loading conditions. Quantitative evaluation of voids de…
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…
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…