  Unlike the vast amount of irradiated material data that exists for stainless
steel internals from LWRs, with high fast neutron flux and an irradiation
temperature of~330oC, the CANDU reactor is unique with a high thermal spectrum
stainless steel components peripheral to the core. In particular, the CANDU
design contains an austenitic stainless steel calandria vessel, which contains
the heavy water moderator at a temperature of 60-80oC. This article explores
the effects of low (60-80oC) and moderate (300-360oC) irradiation temperature
on irradiation induced defects and defect sinks, both in terms of
microstructure and mechanical properties of Grade 304L stainless steel,
irradiated with 3 MeV protons. State-of-the-art microscopy has been applied to
characterize the irradiation defects, and nano-indentation performed to provide
a link with the mechanical properties. It is hypothesized that the interstitial
type of loops that develop is highly temperature dependent, and the formation
of the defect loops is strongly linked with the amount of radiation induced
segregation.
