Abstract
The Simplified Model Test (SMT) approach is an alternative creep-fatigue evaluation method that no longer requires the use of the damage interaction diagram, or D-diagram. The reason is that the combined effects of creep and fatigue are accounted for in the test data by means of a SMT specimen that is designed to replicate or bound the stress and strain redistribution that occurs in actual components when loaded in the creep regime. However, creep-fatigue experiments on SMT key feature articles are specialized and difficult to perform by the general research community. In this paper, two innovative SMT based creep-fatigue experimental methods are developed and implemented. These newly-developed SMT test methods have resolved all the critical challenges in the SMT key feature article testing and enable the potential of further development of the SMT based creep-fatigue evaluation method into a standard testing method. Scoping test results on Alloy 617 and SS 316H using the newly developed SMT methods are summarized and discussed. The concepts of the SMT methodology for creep-fatigue evaluation are explained.
| Original language | English |
|---|---|
| Title of host publication | Codes and Standards |
| Publisher | American Society of Mechanical Engineers (ASME) |
| ISBN (Electronic) | 9780791858929 |
| DOIs | |
| State | Published - 2019 |
| Event | ASME 2019 Pressure Vessels and Piping Conference, PVP 2019 - San Antonio, United States Duration: Jul 14 2019 → Jul 19 2019 |
Publication series
| Name | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP |
|---|---|
| Volume | 1 |
| ISSN (Print) | 0277-027X |
Conference
| Conference | ASME 2019 Pressure Vessels and Piping Conference, PVP 2019 |
|---|---|
| Country/Territory | United States |
| City | San Antonio |
| Period | 07/14/19 → 07/19/19 |
Funding
The research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, under Contract No. DEAC02-06CH11357 with Argonne National Laboratory, managed and operated by UChicago Argonne LLC, and under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory (ORNL), managed and operated by UT-Battelle, LLC. Programmatic direction was provided by the Office of Nuclear Energy. The technical support from Charles S. Hawkins of ORNL is greatly appreciated. This manuscript has been co-authored by UChicago Argonne LLC under Contract No. DE-AC02-06CH11357, and by UT-Battelle LLC, under Contract No. DE-AC0500OR22725, with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, under Contract No. DE-AC02-06CH11357 with Argonne National Laboratory, managed and operated by UChicago Argonne LLC, and under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory (ORNL), managed and operated by UT-Battelle, LLC. Programmatic direction was provided by the Office of Nuclear Energy.
Keywords
- Creep-Fatigue
- Elastic Follow-up
- Simplified Model Test
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