Strain Aging and Neutron Scattering Studies on Irradiated PWR Pressure Vessel Steels
SourceThe combined effects of strain aging and elevated temperature (275 to 290°C) neutron irradiation to doses up to 3.1 × 1019 n/cm2 (>1 MeV) on the Charpy V-notch (Cv) impact properties of commercial A533-B/A508 pressure vessel steels have been investigated. Neutron irradiation suppresses Cv transition shifts associated with nitrogen strain aging, and it is inferred that free nitrogen in the steel is trapped by irradiation-induced point defects or defect clusters. The results imply that strain aging Cv transition shifts need not be regarded as additive to radiation embrittlement shifts in nuclear vessel safety assessments.
The technique of small-angle neutron scattering has been used to study the radiation hardening processes in copper and phosphorus-doped A533-B alloys. The presence of copper leads to the creation of scattering centers ≤1 nm in diameter by irradiation; the volume fraction of scattering centers increases with increasing copper level and is further enhanced by enrichment of bulk nickel content. Addition of 0.07% phosphorus induces radiation hardening and neutron scattering effects comparable with 0.35% copper.