Irradiation Effects on Reactor Structural Materials

The report includes: (1) effect of hold-time on fatigue crack propagation in thermally aged, annealed and 25% cold-worked 304 stainless steel; (2) notch ductility retention of A543 submerged arc and electroslag weld deposits after irradiation; (3) temperature and dose rate dependence of void nucleat...

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Bibliographic Details
Main Author: Steele,Lendell E
Format: Report
Language:English
Subjects:
Crack propagation
Damage
Fatigue(Mechanics)
Fission Reactor Materials
Helium
Irradiation
Metallurgy and Metallography
Nickel
Notch toughness
Radiation effects
Reactor materials
Stainless steel
Steel
Steel 304
Steel A-543
Vanadium
Welds
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Summary:The report includes: (1) effect of hold-time on fatigue crack propagation in thermally aged, annealed and 25% cold-worked 304 stainless steel; (2) notch ductility retention of A543 submerged arc and electroslag weld deposits after irradiation; (3) temperature and dose rate dependence of void nucleation and growth in heavy ion bombarded nickel; (4) studies of the mobility of helium in vanadium; (5) effect of cyclotron-implanted helium on the fatigue behavior of 316 stainless steel; and (6) notch toughness of irradiated 316 stainless steel weld. (Modified author abstract) See also AD-768 290.