Machining of fatigue, creep-fatigue, and creep specimens from a welded Alloy 617 plate with Alloy 617 filler
Program Document
·
OSTI ID:1615637
- Idaho National Laboratory
Welds are inevitable in the design and construction of nuclear reactors. Consequently, welds need to be included in high temperature design methodologies for the construction of nuclear reactors. Two areas needing addressed are the following: (i) An assessment of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section III, Division 5 cyclic design methodology for weldments. (ii) Classification of Alloy 617 weld metal as notch strengthening or weakening.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- B612
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1615637
- Report Number(s):
- INL/MIS-19-55974-Rev000
- Country of Publication:
- United States
- Language:
- English
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