Irradiation Effects on Reactor Structural Materials 1 August 1974 - 31 January 1975

This report, covering research for the period, 1 August 1974 - 31 January 1975 includes: (1) the effect of hold time on fatigue crack propagation in neutron irradiated 20% cold worked Type 316 stainless steel; (2) high fluence assessments of 0.03% copper plate from 30-ton A533-B demonstration melt;...

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Bibliographic Details
Main Author: Steele,Lendell E
Format: Report
Language:English
Subjects:
COATINGS
COPPER
CRACK PROPAGATION
DEFECTS(MATERIALS)
ELECTRON MICROSCOPY
FATIGUE(MECHANICS)
Fission Reactor Materials
FRACTURE(MECHANICS)
ION BOMBARDMENT
Metallurgy and Metallography
MOLYBDENUM
NICKEL
Nickel alloy Incoloy 800
Nickel alloy Inconel 718
NICKEL ALLOYS
NIOBIUM
NOTCH TOUGHNESS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEEL
STEEL
Steel 316
Steel PH13-8Mo
Stress intensity factor
WELDS
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Summary:This report, covering research for the period, 1 August 1974 - 31 January 1975 includes: (1) the effect of hold time on fatigue crack propagation in neutron irradiated 20% cold worked Type 316 stainless steel; (2) high fluence assessments of 0.03% copper plate from 30-ton A533-B demonstration melt; (3) examination of microstructures of Inconel 718, Incoloy 800, PH13-8Mo, Mo and Nb after irradiation in EBR-II; (4) fluence dependence of ion damage in nickel; (5) ionsimulated irradiation-induced creep of reactor structural alloys; and (6) notch ductility and strength of Type 316 stainles steel submerged arc weld deposits. See also report dated Aug 74, AD-786 733.