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A Brief Review of Models Representing Creep of Alloy 617

[+] Author Affiliations
Robert W. Swindeman, Weiju Ren

Oak Ridge National Laboratory, Oak Ridge, TN

Michael J. Swindeman

University of Dayton, Dayton, OH

Paper No. PVP2005-71784, pp. 469-476; 8 pages
doi:10.1115/PVP2005-71784
From:
  • ASME 2005 Pressure Vessels and Piping Conference
  • Volume 6: Materials and Fabrication
  • Denver, Colorado, USA, July 17–21, 2005
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4191-X | eISBN: 0-7918-3763-7
  • Copyright © 2005 by ASME

abstract

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.

Copyright © 2005 by ASME
Topics: Creep , Alloys

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