Irradiation Effects on Reactor Structural Materials.
Quarterly progress rept. 1 May-31 Jul 73,
NAVAL RESEARCH LAB WASHINGTON D C
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The report, covering research for the period 1 May - 31 July 1973, includes 1 fatigue properties of irradiated EBR-2 control rod thimble 304 stainless steel 2 fracture toughness characterization of irradiated stainless steels 3 notch ductility of higher strength steels. Types A543 plate and A508 forging 4 damage produced in iron and iron alloys by neutron irradiation and ion bombardment 5 mircrostructure of helium-implanted annealed and cold worked 316 stainless steel, and 6 determination of neutron flux level in the SM-1 reactor. Modified author abstract
- Metallurgy and Metallography
- Radioactivity, Radioactive Wastes and Fission Products
- Fission Reactor Materials