| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Effect of Dynamic Strain Aging on high-Temperature Mechanical Properties of FeCrAl APMT alloys |
| Author(s) |
Mahmoud Y. Hawary, Abdullah S. Alomari, K.L. Murty |
| On-Site Speaker (Planned) |
Mahmoud Y. Hawary |
| Abstract Scope |
The growing power demand necessitates an increase in the capacity of nuclear power plants. These advanced systems require materials capable of withstanding high operating temperatures and the consequent effects, such as corrosion. The iron-chromium-aluminum (FeCrAl) Kanthal® APMT alloy is a leading candidate as a cladding material in Light Water Reactors (LWRs), offering enhanced accident tolerance, superior high-temperature properties, and better oxidation/corrosion resistance compared to the standard zirconium-based alloys. A thorough understanding of this alloy's behavior under various conditions is crucial for ensuring safety. This study investigates the dynamic strain aging (DSA) and serrated yielding behavior of FeCrAl APMT alloy within a temperature range of 298–973 K and strain rates from 10^-3 to 10^-5 s^-1. The research focuses on how tensile properties and serration types are influenced by temperature and strain rate, utilizing uniaxial tensile tests and subsequent microstructural examinations of both as-received and deformed samples. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Nuclear Materials, Mechanical Properties |