Structural Integrity of Water Reactor Pressure Boundary Components.
- 28 September 1979
- report
- Published by Defense Technical Information Center (DTIC)
Abstract
This report describes research progress in a continuing program to characterize materials properties performance with respect to structural integrity of light water reactor pressure boundary components. progress for this reporting period is summarized in the following areas: (a) postirradiation fracture toughness of IAEA coordinated program steels, (b) Charpy V-notch ductility trends of submerged arc weld deposit with cyclic postirradiation annealing and reirradiation treatments, (c) J-R curve characterization of irradiated submerged arc weld deposits, and (d) evaluation of critical factors in cyclic crack growth rate studies in a pressurized water reactor environment. (Author)Keywords
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