Creep-fatigue behavior of alloy 617 - 18581
- Idaho National Laboratory: P.O. Box 1562, Idaho Falls ID, 83415 (United States)
- Argonne National Laboratory: 9700 S. Cass Ave, Argonne IL 60439 (United States)
Alloy 617 is the leading candidate material for the intermediate heat exchanger for the very high temperature reactor (VHTR). It is thought that creep-fatigue resistance is likely to be the life-limiting material property for this application. As part of evaluating the behavior of this material in the expected service conditions, creep fatigue testing of Alloy 617 was performed at 850 and 950 deg. C for several strain ranges and hold times. Creep-fatigue degradation was observed, characterized by reduced cycles to failure when a hold time was added at peak tensile strain, compared to fatigue values. At 850 deg. C, increasing the tensile hold duration continued to degrade the creep fatigue resistance, at least to the investigated strain controlled hold time of up to 60 minutes at the 0.3% strain range and 240 minutes at the 1.0% strain range. At 950 deg. C, the creep fatigue cycles to failure are not further reduced with increasing hold duration, indicating saturation occurs at relatively short hold times. The creep and fatigue damage fractions have been calculated using the ASME methodology and plotted on a creep fatigue interaction D diagram. The impact of selecting different parameters on calculation of the creep damage fraction has been evaluated and will be discussed in this paper. Additional damage fractions from creep fatigue tests at 800 and 1000 deg. C on a different heat of Alloy 617 have been determined and are plotted on the D diagram along with results of the current testing. The combined data represent a comprehensive evaluation of Alloy 617 behavior under the ASME methodology and result in a consistent creep-fatigue damage envelope. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23032699
- Resource Relation:
- Conference: HTR 2016: International Topical Meeting on High Temperature Reactor Technology, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 10 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
- Country of Publication:
- United States
- Language:
- English
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