Development of new, radiation-tolerant materials that maintain the structural integrity and safety margins over the course of a nuclear power reactor's service life requires the ability to predict degradation phenomena.
Concrete, used in the construction of nuclear power plants (NPPs), may be exposed to radiation emanating from the reactor core. Until recently, concrete has been assumed immune to radiation exposure. Direct evidence acquired on Ar+-ion irradiated …
Model FeCrAl alloys with varying compositions (Fe(10-18)Cr(10-6)Al at.\%) have been neutron irradiated at ∼ 320 to damage levels of ∼ 7 displacements per atom (dpa) to investigate the compositional influence on the formation of irradiation-induced …
Life extension of light water reactors will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), leading to profound microstructural evolution and consequent degradation of macroscopic …
This work presents a detailed analysis of the diffusion fluxes near and at grain boundaries of irradiated Fe-Cr-Ni alloys, induced by preferential atom-vacancy and atom-interstitial coupling. The diffusion flux equations were based on the Perks model …