Fatigue and Fracture Resistance of Stainless Steel Weld Deposits after Elevated-Temperature Irradiation

The fatigue crack growth and fracture resistance of Type 308-16 austenitic stainless steel weld deposits were investigated for 427 deg and 649 deg C neutron irradiation conditions. The welds (63.5 mm thick) were made by the shielded metal arc process and depicted variations in delta ferrite content...

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Bibliographic Details
Main Author: Hawthorne,J R
Format: Report
Language:English
Subjects:
AUSTENITE
CHARPY IMPACT TESTS
CRACK PROPAGATION
DUCTILITY
EMBRITTLEMENT
FERRITES
FRACTURE(MECHANICS)
HIGH TEMPERATURE
IRRADIATION
LPN-DOE-EX-76-A-27-2110
LPN-NRL- 1062-0-0
Mechanics
Metallurgy and Metallography
Notch ductility
NUCLEAR REACTORS
RADIATION
RESISTANCE
SENSITIVITY
STAINLESS STEEL
TOUGHNESS
Weld deposits
WELDMENTS
WELDS
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Summary:The fatigue crack growth and fracture resistance of Type 308-16 austenitic stainless steel weld deposits were investigated for 427 deg and 649 deg C neutron irradiation conditions. The welds (63.5 mm thick) were made by the shielded metal arc process and depicted variations in delta ferrite content from ferrite number 5.2 to 19.0. Specimen irradiations were conducted in the EBR-II reactor in flowing and static sodium environments. Fatigue crack growth resistances at 427 deg and 649 deg C were determined with single-edge-notch (SEN) cantilever fatigue specimens tested in air with a zero-tension-zero loading cycle. Crack growth rates were related to the stress-intensity-factor range. Effects of a tension hold time of 0.5 minute were explored relative to weld behavior under continuous load cycling conditions. Fracture resistance at elevated temperature was investigated through notch ductility and dynamic fracture toughness determinations by Charpy-V and fatigue-precracked Charpy-V test methods respectively.