Irradiation Effects on Reactor Structural Materials 1 August 1974 - 31 January 1975.
Semi-annual progress rept.,
NAVAL RESEARCH LAB WASHINGTON D C
Pagination or Media Count:
This report, covering research for the period, 1 August 1974 - 31 January 1975 includes 1 the effect of hold time on fatigue crack propagation in neutron irradiated 20 cold worked Type 316 stainless steel 2 high fluence assessments of 0.03 copper plate from 30-ton A533-B demonstration melt 3 examination of microstructures of Inconel 718, Incoloy 800, PH13-8Mo, Mo and Nb after irradiation in EBR-II 4 fluence dependence of ion damage in nickel 5 ionsimulated irradiation-induced creep of reactor structural alloys and 6 notch ductility and strength of Type 316 stainles steel submerged arc weld deposits.
- Metallurgy and Metallography
- Fission Reactor Materials