DID YOU KNOW? DTIC has over 3.5 million final reports on DoD funded research, development, test, and evaluation activities available to our registered users. Click
HERE to register or log in.
Accession Number:
AD0672890
Title:
NOTCH DUCTILITY AND TENSILE PROPERTY EVALUATION OF THE PM-2A REACTOR PRESSURE VESSEL.
Descriptive Note:
Interim rept.,
Corporate Author:
NAVAL RESEARCH LAB WASHINGTON D C
Report Date:
1968-06-19
Pagination or Media Count:
23.0
Abstract:
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
Distribution Statement:
APPROVED FOR PUBLIC RELEASE
