A5025031699- Nuclear Materials and Properties
- Fusion materials and technologies
- Advanced ceramic materials synthesis
- Additive Manufacturing and 3D Printing Technologies
- Graphite, nuclear technology, radiation studies
- Aluminum Alloys Composites Properties
- Advanced materials and composites
- High Temperature Alloys and Creep
- Bone Tissue Engineering Materials
- Metallurgy and Material Forming
- Metallurgical Processes and Thermodynamics
- Nuclear reactor physics and engineering
- High-Temperature Coating Behaviors
- Innovations in Concrete and Construction Materials
- Metal Forming Simulation Techniques
- Nuclear Physics and Applications
- Hydrogen embrittlement and corrosion behaviors in metals
- Injection Molding Process and Properties
- Radioactive element chemistry and processing
- Electronic Packaging and Soldering Technologies
Idaho National Laboratory
2024-2025
Missouri University of Science and Technology
2022-2024
Abstract A novel additive manufacturing approach is herein reported for high mechanical strength continuous carbon fiber‐reinforced silicon carbide (C f /SiC) composite materials. Continuous fibers were coated with polycarbosilane (PCS) using a colloidal evaporative deposition process and then coextruded solid content SiC ink. The zeta potential of the ink was adjusted to optimize printing ability suspension. During sintering, small grains whiskers generated in gaps around PCS‐coated fibers,...
Mechanical testing with sub-sized specimens plays an important role in the nuclear industry, facilitating tests confined experimental spaces lower irradiation levels and accelerating qualification of new materials. The reduced size results different material behavior at microscale, mesoscale, macroscale, comparison to standard-sized specimens, which is referred as "specimen effect." Although analytical models have been proposed correlate properties these lack broad applicability across...
Reactor pressure vessel (RPV) steels are critical for maintaining the structural integrity and safety of nuclear reactors, designed to endure extreme conditions over prolonged operational lifetimes. Evaluating mechanical properties RPV frequently involves tests with sub-sized specimens, due size constraints associated irradiated materials. However, reduced specimen dimensions introduce a effect that alters material behavior requires correlating test results full-sized specimens. Although...
High solids loading silicon carbide (SiC)-based aqueous slurries containing only .5 wt. % organic additives were utilized to create specimens of various geometries via an extrusion-based additive manufacturing (AM) technique. Pressureless electric field-assisted sintering was performed densify each specimen without deformation. The combination these techniques produced parts with >98% relative density despite 5 wt.% oxide additives. After sintering, contained the α-SiC and yttrium aluminum...
Mechanical testing with sub-sized specimens plays an important role in the nuclear industry, facilitating tests confined experimental spaces lower irradiation levels and accelerating qualification of new materials. The reduced size results different material behavior at microscale, mesoscale, macroscale, comparison to standard-sized specimens, which is referred as specimen effect. Although analytical models have been proposed correlate properties these lack broad applicability across...
FeCrAl alloys are promising candidates to replace Zr as fuel cladding materials in nuclear light-water reactors. Grain refinement has been indicated improve irradiation resistance. To enhance corrosion resistance well, the effects of grain on steam behavior were investigated this work. Samples Kanthal D alloy (Fe-21Cr-5Al) with two different sizes (coarse-grained and ultrafine-grained) exposed at 1200 °C for 2 hrs. Results indicate improved ultrafine-grained formation a thinner protective Al...