Irradiation Effects on Reactor Structural Materials
The research program of the NRL Metallurgy Division, Reactor Materials Branch, involves a broad study of the effects of nuclear radiation upon materials. The report covering research for the period 1 February - 30 April 1973, includes: The effect of hold time on fatigue crack propagation in 20% cold...
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Sprache: | eng |
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Zusammenfassung: | The research program of the NRL Metallurgy Division, Reactor Materials Branch, involves a broad study of the effects of nuclear radiation upon materials. The report covering research for the period 1 February - 30 April 1973, includes: The effect of hold time on fatigue crack propagation in 20% cold worked stainless steel; the effect of implanted helium on fatigue behavior of TZM alloy; radiation enhanced metastability in a high strength structural alloy, The AEC-CE-NRL Cooperative program on A533-B reactor vessel steel; The transition temperature increase for the SM-1A pressure vessel at reactor shutdown; J-integral characterization of the SM-1A reactor pressure vessel steels; The effect of water vapor on the fatigue strength of irradiated Type 348 stainless steel; The effect of beam scanning on void formation in nickel-ion bombarded nickel. (Modified author abstract)
See also report dated 15 Feb 73, AD-758 355. |
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