About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
High Throughput Nanoindentation Creep Testing in Nuclear Reactor Steels |
Author(s) |
Moujhuri Sau, Eric Hintsala, Douglas Stauffer, Laurent Capolungo, Nathan Mara |
On-Site Speaker (Planned) |
Moujhuri Sau |
Abstract Scope |
Nanoindentation is a high-throughput small-scale alternative to bulk creep testing used for study nanoscale mechanical deformation over the span of seconds or minutes with minimal volumes of materials, allowing for rapid alloy testing and development. Elevated temperature tests were conducted on three different reactor steel candidate materials - an austenitic stainless steel alloy (SS347H), an ODS alloy (MA957) and a FeCrAl alloy (APMT) – to study their nanoscale mechanical response as a function of temperature and strain rate. This time-dependent deformation is quantified by calculating strain rate sensitivity, activation energy and activation volumes. The high-temperature microstructural deformation after indentation was visualized with EBSD and TEM microscopy. The data sets will be discussed in terms of dominant mechanisms responsible for creep and correlated to bulk tensile creep data. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Iron and Steel, Mechanical Properties |