About this Abstract |
Meeting |
2020 TMS Annual Meeting & Exhibition
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Symposium
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Fatigue in Materials: Fundamentals, Multiscale Characterizations and Computational Modeling
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Presentation Title |
Creep-fatigue Behavior of an Advanced Austenitic Stainless Steel (Alloy 709) |
Author(s) |
Zeinab Alsmadi, K.L. Murty |
On-Site Speaker (Planned) |
Zeinab Alsmadi |
Abstract Scope |
The design and operation of high temperature systems that exhibit cyclic thermal stresses due to temperature gradients during start-ups and shut-downs introduce time-dependent effects like creep during on-load periods at elevated temperatures. Next-generation nuclear reactors such as Sodium-Cooled Fast Reactor (SFR) are subjected to creep-fatigue damage in reactor components. Therefore, the structural materials for SFR should have adequate mechanical properties that can withstand typical operating conditions expected in the nuclear reactor core. Fe-25Ni-20Cr (wt.%) advanced austenitic stainless steel (Alloy 709) is a potential candidate as structural material for SFR. Creep-fatigue interaction of the Alloy 709 is investigated by conducting strain-controlled creep-fatigue tests with hold times of 0, 600, 1,800 and 3,600 seconds at strain amplitudes of 0.3%, 0.5% and 0.6% at 750 °C. For each hold time, the number of cycles to failure was found to decrease with increasing strain amplitude. This research is supported by DOE/NEUP project 15-0008582. |
Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |