Irradiation Effects on Reactor Structural Materials.
Semi-annual progress rept. 1 Aug 73-31 Jan 74,
NAVAL RESEARCH LAB WASHINGTON D C
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The report includes 1 effect of hold-time on fatigue crack propagation in thermally aged, annealed and 25 cold-worked 304 stainless steel 2 notch ductility retention of A543 submerged arc and electroslag weld deposits after irradiation 3 temperature and dose rate dependence of void nucleation and growth in heavy ion bombarded nickel 4 studies of the mobility of helium in vanadium 5 effect of cyclotron-implanted helium on the fatigue behavior of 316 stainless steel and 6 notch toughness of irradiated 316 stainless steel weld. Modified author abstract
- Metallurgy and Metallography
- Fission Reactor Materials