Alloy 617 is being considered for the construction of components to operate in the Next Generation Nuclear Plant (NGNP). Service temperatures will range from 650 to 1000°C. To meet the needs of the conceptual designers of this plant, a materials handbook is being developed that will provide information on alloy 617, as well as other materials of interest. The database for alloy 617 to be incorporated into the handbook was produced in the 1970s and 1980s, while creep and damage models were developed from the database for use in the design of high-temperature gas-cooled reactors. In the work reported here, the US database and creep models are briefly reviewed. The work reported represents progress toward a useful model of the behavior of this material in the temperature range of 650 to 1000°C.
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ASME 2005 Pressure Vessels and Piping Conference
July 17–21, 2005
Denver, Colorado, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4191-X
PROCEEDINGS PAPER
A Brief Review of Models Representing Creep of Alloy 617
Robert W. Swindeman,
Robert W. Swindeman
Oak Ridge National Laboratory, Oak Ridge, TN
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Michael J. Swindeman,
Michael J. Swindeman
University of Dayton, Dayton, OH
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Weiju Ren
Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
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Robert W. Swindeman
Oak Ridge National Laboratory, Oak Ridge, TN
Michael J. Swindeman
University of Dayton, Dayton, OH
Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
Paper No:
PVP2005-71784, pp. 469-476; 8 pages
Published Online:
July 29, 2008
Citation
Swindeman, RW, Swindeman, MJ, & Ren, W. "A Brief Review of Models Representing Creep of Alloy 617." Proceedings of the ASME 2005 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication. Denver, Colorado, USA. July 17–21, 2005. pp. 469-476. ASME. https://doi.org/10.1115/PVP2005-71784
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