Fracture Toughness of Pressure Vessel Materials for Light Water Reactors.
Progress rept. for period ending 29 Feb 76,
NAVAL RESEARCH LAB WASHINGTON D C
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This report describes progress in a cooperative research program between the Electric Power Research Institute EPRI and NRL on the fracture toughness of steels for nuclear reactor pressure vessels. For its contribution EPRI furnished a major protion of the materials and test specimens for the study by NRL. The program is also being conducted in collaboration with the Nuclear Regulatory Commission NRC, Office of Nuclear Regulatory Research, and the Office of Naval Research. Related NRC sponsored work of broader scope is underway at NRL. A portion of the NRC work pertaining to the fracture toughness of nuclear pressure boundary materials is also reported here because of its relevance to the subject effort. The principal objectives of this program are 1 to characterize the dynamic fracture initiation toughness K sub Id of three heats of LWR pressure vessel steel, 2 to develop experimental and analytical techniques for the interpretation and analysis of notched, three-point bend specimen behavior under impact loading, and 3 to assess the validity of plane strain K sub Id values as projected from the elastic plastic J integral analysis of smaller specimens. The present report describes progress in the dynamic toughness assessment of program materials by means of 1-in. 25mm bend and precracked Charpy-V specimens. Also described is a one-dimensional, theoretical characterization of the forces and bending moments developed during impact of a notched beam. Author
- Metallurgy and Metallography
- Nuclear Fission Reactors (Power)