This website uses cookies to ensure that you have the best possible experience when visiting the website. View our Privacy policy for more information about this. To accept the use of non-essential cookies, please click "I agree"
Radiation-Induced Damage in Austenitic Structural Steels Used in Nuclear Reactors
Radiation damage to structural alloys in nuclear power plants: mechanisms and remediation
Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30–60 years
Radiation Damage in Austenitic Steels
Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates
Void swelling and irradiation creep in light water reactor (LWR) environments
The effect of dose rate on the response of austenitic stainless steels to neutron radiation
Radiation-induced degradation of stainless steel light water reactor internals
Modeling radiation induced segregation in Ni–Cr model alloys from first principles
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel
Diffusion of He in austenitic stainless steels studied by TDPAC
Fatigue life predictions for irradiated stainless steels considering void swellings effects
A Brief Review on He Ion Irradiation Research of Steel and Iron-Based Alloys in Nuclear Power Plants