IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS.
Quarterly progress rept. 1 May-31 Jul 67,
NAVAL RESEARCH LAB WASHINGTON D C
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The report includes the following 1 through-thickness radiation resistance of two A533 Grade B, Class I steel plates at 550 F, 2 directional notch ductility performance of irradiated 3-12Ni-Cr-Mo and 5Ni-Cr-Mo-V steel plates, 3 radiation sensitivity of A353 9 nickel steel as influenced by percent retained austenite, 4 tensile properties behavior versus postirradiation test temperature of selected structural steels, 5 potential for aging embrittlement of pressure vessel steels, 6 postpressurization test operations on PM-2A reactor pressure vessel, and 7 auxiliary equipment developed for elevated temperature remote tension testing of radioactive specimens. Author
- Metallurgy and Metallography
- Fission Reactor Materials