A Brief Review of Models Representing Creep of Alloy 617

Author:

Swindeman Robert W.1,Swindeman Michael J.2,Ren Weiju1

Affiliation:

1. Oak Ridge National Laboratory, Oak Ridge, TN

2. University of Dayton, Dayton, OH

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.

Publisher

ASMEDC

Cited by 6 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Experimental investigation on microstructural characterization and mechanical properties of plasma arc welded Inconel 617 plates;High Temperature Materials and Processes;2022-01-01

2. Material Performance in Helium-Cooled Systems;Reference Module in Materials Science and Materials Engineering;2019

3. Material Performance in Helium-Cooled Systems;Comprehensive Nuclear Materials;2019

4. Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems;Journal of Pressure Vessel Technology;2014-06-24

5. Material Performance in Helium-Cooled Systems;Comprehensive Nuclear Materials;2012

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