Simulation and characterization of irradiation damage in stainless steels using proton irradiation

Stainless steels (SS) components exposed to neutron irradiation environment e.g. the core of light water reactors (LWRs) are susceptible to irradiation damage like radiation induced segregation (RIS). Neutron irradiation results in generation of point defects far in excess of their equilibrium concentration at operating temperature range. i.e., 280 - 300 degC. Diffusion of point defects at these temperatures results in the formation of chromium depleted regions at the grain boundaries and is a major factor contributing to irradiation assisted stress corrosion cracking (IASCC). This paper describes the findings of these recent experiments of proton irradiation in FOTIA and Pelletron and characterization of RIS