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The Charpy-V (Cv) notch ductility and tensile properties of three reactor pressure vessel (RPV) steel materials were determined for the 288°C (550°F) irradiated (I), 288°C (550°F) irradiated + 454°C (850°F) -168 h postirradiation annealed (IA), and 288°C (550°F) reirradiated (IAR) conditions. Total fluences of the I condition and the IAR condition were, respectively, 3.33 × 1019 n/cm2 and 4.18 × 1019 n/cm2, E > 1 MeV. The irradiation portion of the IAR condition represents an incremental fluence increase of 1.05 × 1019 n/cm2, E > 1 MeV, over the I-condition fluence. The annealing treatment produced full Cv upper shelf recovery and full or nearly full recovery in the Cv 41 J (30 ft-lb) transition temperature. The Cv transition temperature increases produced by the reirradiation exposure were 22% to 43% of the increase produced by the first cycle irradiation exposure. A somewhat greater radiation embrittlement sensitivity and a somewhat greater reirradiation embrittlement sensitivity were exhibited by the low nickel content plate than the high nickel content plate. The IAR-condition properties of the surface vs. interior regions of the low nickel content plate are also compared.
annealing, embrittlement, radiation damage, mechanical properties
Project Manager, Electric Power Research Institute, Charlotte, North Carolina
Materials Engineering Associates, Inc., Lanham, Maryland
Senior Member of Technical Staff, Sandia National Laboratories, Albuquerque, New Mexico