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Title: Overview of Alloy 617 Notched Specimen Testing

S&T Accomplishment Report ·
DOI:https://doi.org/10.2172/1484717· OSTI ID:1484717

Prior to use in high temperature nuclear applications, Alloy 617, which is currently undergoing approval for inclusion in codes and regulations related to high temperature construction, 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. This work has shown that at short time intervals (1000-2500 hours), 617 is notch strengthening and will fail preferentially at locations away from the notch, provided that diameters are similar (resulting in similar stresses). 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, while not fully completed, 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 Office of Nuclear Energy (NE)
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1484717
Report Number(s):
INL/EXT-17-43070-Rev000
Country of Publication:
United States
Language:
English