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AbstractAbstract
[en] The usefulness of intermediate annealing to periodically mitigate the deleterious effects of nuclear radiation on reactor pressure vessel steels is explored. Test materials are intermediate and high copper content weld deposits made commercially. Irradiation and reirradiation exposures were at 288 degrees C. Annealing-induced properties recovery and resistance to reembrittlement by irradiation are qualified for 454 degrees C and 399 degrees C heat treatments and a total fluence of 2.7 x 1019n/cm2. Tendencies toward a saturation of radiation embrittlement were observed in annealed material. With 454 degrees C annealing, embrittlement levels were lower than those observed after irradiation to 1.5 x 1019n/cm2 without intermediate annealing. The method shows high promise for radiation-sensitive pressure vessel steels for increasing their fracture-safe service lifetimes. 22 refs., 27 figs., 5 tabs
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Nov 1989; 193 p; MEA--2364; NTIS, PC A10/MF A01 - GPO as TI90003284; OSTI; INIS
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Report
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Numerical Data
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ANNEALING, EMBRITTLEMENT, EXPERIMENTAL DATA, FABRICATION, HIGH TEMPERATURE, IMPACT TESTS, IRRADIATION, LIFETIME, MATERIALS TESTING, MECHANICAL PROPERTIES, NEUTRON FLUENCE, NOTCHES, OPTIMIZATION, PRESSURE VESSELS, PULSTAR-BUFFALO REACTOR, RADIATION EFFECTS, RADIATION PROTECTION, REACTOR MATERIALS, REACTOR SAFETY, SPECIFICATIONS, STEEL-MNNIMO, TEMPERATURE DEPENDENCE, THERMAL DEGRADATION, WELDED JOINTS
ALLOYS, CARBON ADDITIONS, CONTAINERS, DATA, ENRICHED URANIUM REACTORS, HEAT TREATMENTS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, JOINTS, LOW ALLOY STEELS, MANGANESE ALLOYS, MATERIALS, MECHANICAL TESTS, MOLYBDENUM ADDITIONS, NICKEL ADDITIONS, NUMERICAL DATA, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, STEELS, TESTING, WATER COOLED REACTORS, WATER MODERATED REACTORS
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