Photo from wikipedia
Abstract Austenitic chromium-nickel 321, 316 and 304 stainless steels used for internals of PWR (pressurized water reactor) and WWER (water-water energetic reactor) reactors were irradiated to 4–125 dpa in different… Click to show full abstract
Abstract Austenitic chromium-nickel 321, 316 and 304 stainless steels used for internals of PWR (pressurized water reactor) and WWER (water-water energetic reactor) reactors were irradiated to 4–125 dpa in different neutron energy spectra and investigated by impact bending tests of miniature specimens. Relying on these tests, the effects of neutron dose and neutron energy spectrum on the intergranular fracture energy determining grain boundary strength have been analyzed. Two neutron spectra were considered. One spectrum is typical of the core of light water moderated reactors PWR and WWER, another spectrum is typical of the core of fast neutron reactors (FR). A correlation between resistance to stress corrosion cracking (SCC) and grain boundary strength in irradiated chromium-nickel 321, 316 and 304 stainless steels has been found.
Journal Title: Engineering Failure Analysis
Year Published: 2021
Link to full text (if available)
Share on Social Media: Sign Up to like & get
recommendations!