About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2025
|
| Presentation Title |
Mechanisms-Based Creep-Fatigue Analysis of Alloy 617 for Advanced High-Temperature Nuclear Applications |
| Author(s) |
Tamim Hossain, Intisher Al-Tahmid Omi, Mahmud Hasan Ovi, Silvana Tabares Burgos, Hoon Lee, James F. Stubbins |
| On-Site Speaker (Planned) |
James F. Stubbins |
| Abstract Scope |
The objective of this research is to quantify and model damage caused by creep-fatigue interactions in Nickel-based Alloy 617 at high-temperatures. The characterization of the performance depends on loading patterns, environmental factors, as well as microstructural evolution at various levels of “damage”. With experimental investigations across a spectrum of stress levels, loading patterns and temperatures, we aim to develop a mechanisms-based approach for creep-fatigue analysis as the basis for extending the ASME allowable high temperature service limits. This methodology will enable extended service in advanced nuclear systems, where creep-fatigue represents a critical
design limitation. Elevated temperature mechanical testing and the evolution of deformation microstructures will be supplemented by crystal plasticity modeling, to describe bulk deformation responses. This approach can be extended to component-level deformation analysis, marking a significant advancement beyond current analysis methods reliant on fatigue with hold-time
protocols. Our study employs a novel approach, sequentially evaluating creep and fatigue loading, to better understand creep-fatigue interaction damage. Cyclic stress-strain tests at elevated temperatures coupled with Digital Image Correlation (DIC) are used to monitor stress concentration and relaxation during testing. Microstructural evolution has been performed to distinguish the separate and combined effects of creep and fatigue loading patterns. This
methodology should be applicable for qualification of other high temperature structural alloys for nuclear applications. |
| Proceedings Inclusion? |
Undecided |