Abstract
Iron-chromium-aluminum (FeCrAl) alloys are promising as an accident-tolerant fuel cladding for loss-of-coolant accident scenarios; however, limited data are available on the acting deformation mechanisms for this class of materials after neutron irradiation. Here, in situ tensile test experiments were conducted with specimens irradiated at ~1.8 dpa at typical light water reactor temperatures. Selected regions of interest were examined at different strain levels, aiming to investigate the impact of irradiation on acting deformation mechanisms. The fine material microstructure was investigated via transmission electron microscopy. Dislocation structure, radiation-induced defects, and α′-phase morphology were investigated in detail and compared with scanning electron microscopy-electron backscatter diffraction and mechanical test results.
| Original language | English |
|---|---|
| Pages | 339-345 |
| Number of pages | 7 |
| State | Published - 2019 |
| Externally published | Yes |
| Event | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States Duration: Aug 18 2019 → Aug 22 2019 |
Conference
| Conference | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 |
|---|---|
| Country/Territory | United States |
| City | Boston |
| Period | 08/18/19 → 08/22/19 |
Funding
This research was sponsored by the US Department of Energy, Office of Nuclear Energy, for the Nuclear Energy Enabling Technologies program’s Reactor Materials effort. A portion of the irradiation campaign, including capsule opening and radioactive specimen handling, was sponsored by the Advanced Fuel Campaign of the Nuclear Technology Research and Development program. Authors would like to thank Dr A. Nelson (ORNL) and Dr. M. Sokolov (ORNL) for discussing the results, providing fruitful comments, and reviewing the paper; L. Varma (ORNL) for valuable help in manuscript preparation; and staff of the Irradiated Materials Examination and Testing facility and LAMDA (Low Activation Materials Design and Analysis Laboratory) for their continuing support. Dalong Zhang would also like to acknowledge the support by the U.S. Department of Energy, Office of Fusion Energy Sciences, under contracts DE-AC06-76RLO1830 and DE-FG03-94ER54275. This research was sponsored by the US Department of Energy, Office of Nuclear Energy, for the Nuclear Energy Enabling Technologies program’s Reactor Materials effort. A portion of the irradiation campaign, including capsule opening and radioactive specimen handling, was sponsored by the Advanced Fuel Campaign of the Nuclear Technology Research and Development program. Authors would like to thank Dr A. Nelson (ORNL) and Dr. M. Sokolov (ORNL) for discussing the results, providing fruitful comments, and reviewing the paper; L. Varma (ORNL) for valuable help in manuscript preparation; and staff of the Irradiated Materials Examination and Testing facility and LAMDA (Low Activation Materials Design and Analysis Laboratory) for their continuing support. Dalong Zhang would also like to acknowledge the support by the U.S. Department of Energy, Office of Fusion Energy Sciences, under contracts DE-AC06-76RLO1830 and DE-FG03-94ER54275. This manuscript has been authored by UT-Battelle LLC under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This manuscript has been authored by UT-Battelle LLC under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
| Funders | Funder number |
|---|---|
| DOE Public Access Plan | |
| U.S. Department of Energy | |
| Office of Nuclear Energy | |
| Fusion Energy Sciences | DE-FG03-94ER54275, DE-AC06-76RLO1830 |
| Oak Ridge National Laboratory | |
| UT-Battelle | DE-AC05-00OR22725 |