Irradiation Effects on Reactor Structural Materials

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 stain...

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Bibliographic Details
Main Author: Steele,Lendell E
Format: Report
Language:English
Subjects:
CRACK PROPAGATION
CREEP
ELASTIC PROPERTIES
FATIGUE(MECHANICS)
Ferrite
Fission Reactor Materials
FORGING
IMPURITIES
Metallurgy and Metallography
NEUTRON IRRADIATION
NICKEL
NICKEL ALLOYS
NOTCH TOUGHNESS
RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEEL
Steel 316
Swelling
TEST METHODS
TOUGHNESS
WELDS
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Summary: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. See also report dated Feb 75, AD-A010 510.