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U.S. Department of Energy
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Irradiation effects on reactor structural materials. Semiannual progress report, 1 Feb--31 Jul 1975

Technical Report ·
OSTI ID:7273701
This report, covering research for the period, 1 February to 31 July 1975, includes: (1) the effect of hold time on fatigue crack propagation in neutron irradiated Type 316 stainless steel; (2) the simulation of irradiation-induced creep in nickel; (3) the elastic plastic toughness of Type 316 stainless steel forging; (4) swelling in dilute binary alloys; and (5) the influence of delta ferrite content on notch toughness of austenitic stainless steel weldments.
Research Organization:
Naval Research Lab., Washington, D.C. (USA)
OSTI ID:
7273701
Report Number(s):
AD-A-015619; NRL-MR-3110
Country of Publication:
United States
Language:
English