Alloy 617 is the leading candidate material for an intermediate heat exchanger for the very high temperature reactor (VHTR). As part of evaluating the behavior of this material in the expected service conditions, creep–fatigue testing was performed. The cycles to failure decreased compared to fatigue values when a hold time was added at peak tensile strain. At 850°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°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 and plotted on a creep–fatigue interaction D–diagram. Test data from creep–fatigue tests at 800 and 1000°C on an additional heat of Alloy 617 are also plotted on the D–diagram.
Skip Nav Destination
ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5041-1
PROCEEDINGS PAPER
Determination of the Creep-Fatigue Interaction Diagram for Alloy 617
J. K. Wright,
J. K. Wright
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
L. J. Carroll,
L. J. Carroll
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
T.-L. Sham,
T.-L. Sham
Argonne National Laboratory, Lemont, IL
Search for other works by this author on:
N. J. Lybeck,
N. J. Lybeck
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
R. N. Wright
R. N. Wright
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
J. K. Wright
Idaho National Laboratory, Idaho Falls, ID
L. J. Carroll
Idaho National Laboratory, Idaho Falls, ID
T.-L. Sham
Argonne National Laboratory, Lemont, IL
N. J. Lybeck
Idaho National Laboratory, Idaho Falls, ID
R. N. Wright
Idaho National Laboratory, Idaho Falls, ID
Paper No:
PVP2016-63704, V005T12A004; 10 pages
Published Online:
December 1, 2016
Citation
Wright, JK, Carroll, LJ, Sham, T, Lybeck, NJ, & Wright, RN. "Determination of the Creep-Fatigue Interaction Diagram for Alloy 617." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop. Vancouver, British Columbia, Canada. July 17–21, 2016. V005T12A004. ASME. https://doi.org/10.1115/PVP2016-63704
Download citation file:
61
Views
0
Citations
Related Proceedings Papers
Related Articles
Modeling of the Behavior of a Welded Joint Subjected to Reverse Bending Moment at High Temperature
J. Pressure Vessel Technol (May,2007)
High Temperature Properties and Constitutive Equations for 1 Cr-1/2 Mo Steel
J. Pressure Vessel Technol (August,1978)
Alloy 617 Creep–Fatigue Damage Evaluation Using Specimens With Strain Redistribution
J. Pressure Vessel Technol (April,2015)
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Start-Up, Shutdown, and Lay-Up
Consensus on Pre-Commissioning Stages for Cogeneration and Combined Cycle Power Plants
Understanding the Problem
Design and Application of the Worm Gear