Radiation-induced degradation of stainless steel light water reactor internals

In order to provide a scientific basis for proposed life extension of current light water reactors, the radiation-induced degradation of stainless steel reactor internals will be discussed. A brief review of the basic radiation damage effects in stainless steels at LWR relevant conditions will be presented. It will be discussed how these basic effects result in the key degradation modes that have been identified by light water reactor experience to date, as well as the possibility for more severe degradation or new forms of degradation under extended service conditions. The forms of degradation that will be discussed include radiation hardening, embrittlement, dimensional stability (e.g., creep and swelling), radiation-induced segregation and precipitation, transmutation effects and irradiation-induced stress corrosion cracking.