A5007324385- Fusion materials and technologies
- Nuclear Materials and Properties
- Advanced Materials Characterization Techniques
- Ion-surface interactions and analysis
- Nuclear materials and radiation effects
- Graphite, nuclear technology, radiation studies
- Electronic and Structural Properties of Oxides
- Nuclear and radioactivity studies
- Hydrogen embrittlement and corrosion behaviors in metals
- Nuclear reactor physics and engineering
- High-Temperature Coating Behaviors
- Radiation Shielding Materials Analysis
- Metal and Thin Film Mechanics
- High Temperature Alloys and Creep
- High Entropy Alloys Studies
- Electron and X-Ray Spectroscopy Techniques
- Thin-Film Transistor Technologies
- Silicon and Solar Cell Technologies
- Radioactive element chemistry and processing
- MXene and MAX Phase Materials
- Aluminum Alloys Composites Properties
- Microstructure and mechanical properties
- Advanced ceramic materials synthesis
- Advanced materials and composites
- Ferroelectric and Piezoelectric Materials
Oak Ridge National Laboratory
2015-2024
University of Manchester
2022-2024
Government of the United States of America
2019-2022
Naval Research Laboratory Materials Science and Technology Division
2019
University of Oxford
2011-2017
Oxfam
2014
University of Salford
2005-2010
Pacific Northwest National Laboratory
2010
Grain growth, oxygen stoichiometry, and phase stability of nanostructurally stabilized cubic zirconia (NSZ) are investigated under 2 MeV Au-ion bombardment at 160 400 K to doses up 35 displacements per atom (dpa). The NSZ films produced by ion-beam-assisted deposition technique room temperature with an average grain size 7.7 nm. increases irradiation dose $\ensuremath{\sim}30\text{ }\text{nm}$ $\ensuremath{\sim}35\text{ }\text{dpa}$. Slower growth is observed irradiations, as compared...
The growth of advanced energy technologies for power generation is enabled by the design, development, and integration structural materials that can withstand extreme environments, such as high temperatures, radiation damage, corrosion. High-entropy alloys (HEAs) are a class in which suitable chemical elements four or more numbers mixed to typically produce single-phase concentrated solid solution (CSAs). Many these exhibit good tolerance like limited void swelling hardening up relatively...
To simulate neutron and helium damage in a fusion reactor first wall sequential self-ion implantation up to 13 dpa followed by helium-ion 3000 appm was performed produce damaged layers of ∼2 μm depth pure tungsten. The hardness these measured using nanoindentation studied transmission electron microscopy. Substantial increases were seen implanted regions, with smaller regions which had already been implanted, thus, containing pre-existing dislocation loops. This suggests that, for the same...
Beginning with Chicago Pile I, graphite has been used as a moderator material in nuclear power stations and is considered potential for use future Generation IV advanced reactors. The microstructure of responsible much its mechanical thermo-physical properties, how it responds to irradiation. To understand microstructure, necessary porosity at the macro- micro-scales; porosity, characterize morphological connectivity void content two main phases graphite: filler binder. Here, using several...
The unraveling disorder-driven grain growth mechanism may be utilized to control sizes and tailor the functionality of nanocrystalline materials.
Phase stability of NiCoFeCr and Al0.12NiCoFeCr single phase high entropy alloys (HEAs) was studied under 3 MeV Ni2+ irradiation at 500 °C to a fluence 1 × 1017/cm2 reaching peak dose ~100 displacements per atom (dpa). Transmission electron microscopy (TEM) diffraction pattern scanning transmission microscopy-energy dispersive X-Ray spectroscopy (STEM-EDS) were utilized detect any second phases that formed in the irradiated regions specimens. While alloy has remained stable irradiation,...