Alloy 617 is an attractive material for the construction of components to operate in both ultra-supercritical steam power boilers and internal components for Generation IV nuclear power and hydrogen production systems. The database for this material is very extensive and is being re-examined in terms of newly developed continuum damage models. Here, the various damage mechanisms that operate at high temperatures are considered on an individual basis and incorporated in damage rate formulations that may be integrated to produce strain versus time response. The work reported represents progress toward a useful model of the behavior of this material in the temperature range of 650 to 1000°C.

* Work sponsored by the U.S. Department of Energy, Office of Fossil Energy under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT-Battelle, LLC.