A pure Fe-Cr-Ni alloy, P-containing model austenitic stainless steels and AISI316 were irradiated at 493 or 613K. At 493K, the density of defect clusters increased with irradiation dose, but there was no significant difference in loop density or loop size among the various materials. At 613K, interstitial-type dislocation loops and phosphides were formed in the pure ternary and P-containing alloys, respectively, in the early stages of irradiation. The results suggested that defect cluster formation at 493 and 613K was controlled mainly by cascade damage and by the long-range migration of free point defects, respectively.

Fluence Dependence of Defect Evolution in Austenitic Stainless Steels during Fission Neutron Irradiation. H.Watanabe, T.Muroga, N.Yoshida: Journal of Nuclear Materials, 1999, 271-272, 381-4