Irradiation Effects on Reactor Structural Materials.
Quarterly progress rept. 1 Nov 72-31 Jan 73,
NAVAL RESEARCH LAB WASHINGTON D C
Pagination or Media Count:
The report, covering research for the period 1 November 1972 - 31 January 1973, includes 1 postirradiation notch ductility assessments of austenitic stainless steel weldments, 2 studies of fatigue resistance of neutron irradiated cold worked Type 304 stainless steel, 3 environmental exposure studies of candidate first-wall materials in the Princeton ST Tokamak, 4 observations of bubble growth in 216 stainless steel implanted with helium, and 5 helium-Microstructure interaction in cyclotron-implanted, annealed, and cold-worked 316 stainless steel. Author Modified Abstract
- Metallurgy and Metallography
- Radioactivity, Radioactive Wastes and Fission Products
- Fission Reactor Materials