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NOTCH DUCTILITY AND TENSILE PROPERTY EVALUATION OF THE PM-2A REACTOR PRESSURE VESSEL.
NAVAL RESEARCH LAB WASHINGTON D C
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Following the pressurization-to-failure testing of the PM-2A reactor pressure vessel, several sections of steel were removed from the vessel wall in a region adjacent to the artificial defect. Charpy V-notch and tension test specimens machined from one of these sections have been evaluated. The irradiated-condition 30 ft-lb transition temperatures for the 14-thickness nearest to the core and 34-thickness locations in the vessel wall were 115F and 55F, respectively, for measured fission-spectrum fluences of 7.3 and 4.0 X 10 to the 18th power nsq cm greater than 1 Mev. The 14-thickness properties and fluence most nearly represented those at the tip of the artificial defect. The 0.2 yield strength for the 14-thickness location was 97,620 psi at -20F failure temperature and 92,200 psi at 72F temperature at time of acid-sharpening treatment of artificial defect. Significant uniform elongation, reduction of area, and elongation per 1 in. were retained by the steel. An assessment of the stress, temperature, and flaw-size conditions for the PM-2A failure, as indexed by the irradiated-condition mechanical properties, indicates that the failure is in agreement with the generalized fracture analysis diagram. Author
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