NEUP CINR-23-29009: Investigation of intergranular cracking of highly irradiated austenitic stainless steels – materials of pressurized water reactors – in ambient conditions

During several testing campaigns of irradiated materials (past and current), it has been observed that highly irradiated (>10 dpa) austenitic stainless steels can undergo intergranular brittle fracture at ambient conditions. This project is intended to support continued operation of light water reactors via analyzing and mitigating this phenomenon.

Additional Info

Field	Value
Awarded Institution	Oak Ridge National Laboratory
PI	Maxim Gussev