Skip to main content
SHARE
Publication

A BRIEF REVIEW OF MODELS REPRESENTING CREEP OF ALLOY 617...

by Robert W Swindeman, Michael Swindeman, Weiju Ren
Publication Type
Conference Paper
Publication Date
Page Numbers
469 to 476
Volume
6
Conference Name
2005 ASME Pressure Vessels and Piping Division Conference
Conference Location
Denver, Colorado, United States of America
Conference Date
-

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.