Notch Effects on the Short Term Rupture Properties of Alloy 617 Base Metal and Weldments
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
Alloy 617 is currently undergoing approval for inclusion in the ASME Boiler and Pressure Vessel Code in Section III Division 5 for use in high temperature nuclear reactors. Prior to use in construction of these reactors, however, it must be approved by the Nuclear Regulatory Commission. Several concerns relating to the effects of geometric discontinuities, such as notches and multi-axial stress states (as opposed to uniaxial stress states typically present in laboratory run creep tests), must first be addressed. Alloy 617 has been found to be notch-strengthening in short term (1000-2500 hour) creep testing for both base metal and weld metal and will fail preferentially in a straight gauge section rather than at a sharp notch, provided that the applied stresses are similar in both the straight gauge and notch sections. Additionally, specimens designed with semi-circular notches (or U notches, as they are referred to in this report) to impose multi-axial stress states on the specimen during creep-testing were found to either maintain similar creep-rupture-lives as uniaxial stress specimens tested at similar conditions, or have creep-rupture-lives that were significantly longer. This work shows that notches and multi-axial stress states do not appear to raise concerns with relation to the use of design rules created for Alloy 617 using smooth, straight-gauge test specimens and uniaxial creep tests.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1475410
- Report Number(s):
- INL/EXT-18-51278-Rev000; TRN: US1902623
- Country of Publication:
- United States
- Language:
- English
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