Abstract
An advanced accident-tolerant FeCrAl alloy, C35 M (Fe–13Cr–10Al–1Mo, at %), and its laser-fusion weldments were studied after neutron irradiation up to 1.8 dpa at 357 °C to evaluate the radiation damage and α′-precipitation kinetics. Results show that the densities of α′ in the fusion zone (FZ) and the heat-affected zone (HAZ) were only a third of that in the base material, i.e., 2.3 × 1024 m−3. Density of dislocation loops in the FZ and HAZ were less than half of that in base material. The size of α′ precipitates and the dislocation loops were found to be smaller in base material, compared to FZ and HAZ. The variances in microstructural response within the different regions were attributed to initial as-welded states of each region, indicating the impact of the pre-irradiation condition on radiation response in FeCrAl alloys.
| Original language | English |
|---|---|
| Article number | 151784 |
| Journal | Journal of Nuclear Materials |
| Volume | 527 |
| DOIs | |
| State | Published - Dec 15 2019 |
Funding
Notice: 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 ). The authors would like to thank ORNL's Irradiated Materials Examination and Testing facility and Low Activation Materials Development and Analysis laboratory staff for their continuing support of this research. Careful reviews by Dr. Caleb Massey and Dr. Jonathan Poplawsky are highly appreciated. Metallographic and compositional data provided by Dr. Yukinori Yamamoto and Dr. Zhiqian Sun are acknowledged. This research was performed, in part, using instrumentation (FEI Talos) provided by the Department of Energy (DOE), Office of Nuclear Energy, Fuel Cycle R&D Program , and the Nuclear Science User Facilities . Research was sponsored by the DOE Office of Nuclear Energy, Advanced Fuel Campaign of the Nuclear Technology R&D program . Neutron irradiation of FeCrAl alloys at ORNL's HFIR user facility was sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, DOE . The authors would like to thank ORNL's Irradiated Materials Examination and Testing facility and Low Activation Materials Development and Analysis laboratory staff for their continuing support of this research. Careful reviews by Dr. Caleb Massey and Dr. Jonathan Poplawsky are highly appreciated. Metallographic and compositional data provided by Dr. Yukinori Yamamoto and Dr. Zhiqian Sun are acknowledged. This research was performed, in part, using instrumentation (FEI Talos) provided by the Department of Energy (DOE), Office of Nuclear Energy, Fuel Cycle R&D Program, and the Nuclear Science User Facilities. Research was sponsored by the DOE Office of Nuclear Energy, Advanced Fuel Campaign of the Nuclear Technology R&D program. Neutron irradiation of FeCrAl alloys at ORNL's HFIR user facility was sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, DOE.
Keywords
- Accident tolerant
- Dislocation loops
- FeCrAl
- Precipitation
- Welding