Irradiation Effects on Reactor Structural Materials.
Quarterly progress rept. 1 Aug-31 Oct 70,
NAVAL RESEARCH LAB WASHINGTON D C
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The report, covering research for the period 1 August - 31 October 1970, includes 1 initial radiation damage surveillance results for the MH-1A reactor vessel, 2 development of a reference fluence decrease through a reactor vessel wall, 3 analysis of the fluence gradient in terms in terms of fracture behavior, including fracture extension resistance for the through-wall vessel properties, 4 correlation of Charpy-V and dynamic tear test results for reactor steels after irradiation, 5 true stress-natural strain determinations for several high temperature alloys irradiated in the EBR-II reactor, and 6 the nature of dislocation loop growth during annealing of irradiated vanadium. Author
- Metallurgy and Metallography
- Fission Reactor Materials