Structural Integrity of Water Reactor Pressure Boundary Components.
Progress rept. ending 31 Aug 77,
NAVAL RESEARCH LAB WASHINGTON D C
Pagination or Media Count:
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 evaluation of critical factors in crack growth rate studies in a pressurized water reactor environment irradiation and postirradiation annealing heat treatment study of the toughness of pressure vessel steels having a low upper shelf level exploratory investigation of notch ductility changes in A508-2 forgings compositional variables affecting upper shelf toughness and investigation of warm prestress phenomenon as a means to limit crack extension in a vessel during a loss-of-coolant accident. Author
- Containers and Packaging
- Fission Reactor Materials