About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
| Presentation Title |
Preliminary Studies on Creep Behavior of Commercial FeCrAl Alloy (APMT) |
| Author(s) |
Hamdy Abouelella, Benjamin Beeler, Jacob Eapen, Korukonda Murty |
| On-Site Speaker (Planned) |
Hamdy Abouelella |
| Abstract Scope |
FeCrAl alloys are being considered accident-tolerant fuel-cladding for the current light water reactors (LWRs). The chemical passivity of FeCrAl in a water-steam environment allows a larger time window for accident response. In this work, the high-temperature creep behavior of a commercial FeCrAl alloy (Kanthal APMT) is investigated. Uniaxial tensile creep tests are conducted at four different temperatures (575℃, 600℃,625℃,650℃) and over a range of stresses from 50 MPa to 400 MPa. Transitions in creep mechanisms are noted with a stress exponent of ~3 at low stresses, which increases to ~8 at intermediate stresses, and finally to ~14 at high stresses. While precipitation hardening is believed to be the rate-controlling mechanism in the high-stress regime, dislocation glide controls the creep at the lower stresses. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Nuclear Materials, Iron and Steel |