In this work, the nanoscale microstructure of an advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy (SM13 heat) with nominal composition Fe–14Cr–3W-0.4Ti-0.3Y2O3 (wt. \%) has been characterized by atom probe tomography (APT) before and …
In early 2017, the Fusion Energy Sciences Advisory Committee (FESAC), an advisory committee to the United States Department of Energy, was charged with identifying transformative enabling capabilities (TECs) “that could promote efficient advance …
Iron–chromium–aluminum (FeCrAl) alloys are of interest in the nuclear industry for their excellent corrosion and oxidation resistance. FeCrAl alloys have been considered for nuclear applications such as accident tolerant fuel cladding, structural …
Advanced manufacturing (AM) is a disruptive manufacturing process often referred to as “the next industrial revolution” because of its ability to fabricate components with complex geometries and site-specific materials and properties. While other …
Dual ion irradiations using 5 MeV defocused Fe2+ ions and co-injected He2+ ions were conducted on a ferritic-martensitic steel alloy, T91, in the temperature range of 406 °C–570 °C over a damage range of 14.6–35 dpa followed by characterization of …
The nuclear incident at the Fukushima Daiichi nuclear power plant has created a strong push for accident-tolerant fuel cladding to replace current zirconium-based cladding. A current near-term focus on iron-chromium-aluminum (FeCrAl) alloys. …
Silicon carbide (SiC) is a primary candidate for passive irradiation temperature monitoring, and continuous dilatometry (CD) has been proposed as the key method for extracting irradiation temperatures from SiC thermometry samples. The CD method was …
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 $\alpha$′-precipitation kinetics. Results …
Ferritic/martensitic (FM) steels are being targeted for use in a range of advanced reactor concepts as cladding and structural components. FM steels for nuclear reactor applications have historically been produced using traditional methods (e.g., …