A5033748941- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Radioactive element chemistry and processing
- Fusion materials and technologies
- Electron and X-Ray Spectroscopy Techniques
- Nuclear Physics and Applications
- Silicon Carbide Semiconductor Technologies
- CO2 Sequestration and Geologic Interactions
- Advanced Materials Characterization Techniques
- Intermetallics and Advanced Alloy Properties
- Semiconductor materials and devices
- Aluminum Alloy Microstructure Properties
- Arsenic contamination and mitigation
- High Temperature Alloys and Creep
- Photoacoustic and Ultrasonic Imaging
- Mine drainage and remediation techniques
- Molten salt chemistry and electrochemical processes
- Cell Image Analysis Techniques
- Soil and Unsaturated Flow
- Electrical and Bioimpedance Tomography
- Luminescence Properties of Advanced Materials
- Ion-surface interactions and analysis
- Bone Tissue Engineering Materials
- Silicon and Solar Cell Technologies
- Heat transfer and supercritical fluids
Idaho National Laboratory
2010-2024
University of Florida
2022
Delft University of Technology
2021
Joint Research Centre
2018
University of Miami
1993
Abstract Oxygen-metal ratios are important to the study of irradiated nuclear oxide fuel. Critical performance metrics such as thermal conductivity, constituent redistribution, and melting temperature depend on degree departure from UO 2.00 stoichiometry in which direction (hyper- or hypo-stoichiometric) has occurred. This examined three sintered pellets with compositions , 2.02 2.21 one un-sintered pellet a composition 2.16 . When analysed via electron probe microanalysis, Al-coated...
Induced precipitation of phosphate minerals to scavenge trace elements from groundwater is a potential remediation approach for contaminated aquifers. The success engineered schemes depends on the particular phases generated, their rates formation, and long term stability. purpose this study was examine calcium under conditions representative natural groundwater. Because microorganisms are present in groundwater, because some proposed mineral rely stimulation native microbial populations, we...
A novel sample mount design with integrated fiducial marks and software for assisting operators in easily efficiently locating points of interest established previous analytical sessions is described. The holder were evaluated experiments to demonstrate the utility ease finding same two different microscopy instruments. Also, numerical analysis expected errors determining position unbiased by a human operator was performed. Based on results, issues related acquiring reproducibility best...
Transmutation nuclear fuels contain weight percentage quantities of actinide elements, including Pu, Am and Np. Because the complex spectra presented by elements using electron probe microanalysis (EPMA), it is necessary to have relatively pure element standards facilitate overlap correction accurate quantitation. Synthesis oxide complicated their multiple oxidation states, which can result in inhomogeneous or that are not stable at atmospheric conditions. PuP4 results a specimen exhibits...
HIGHLIGHTS• EPMA and Q-ICP-MS analyses of U, Pu, Zr in irradiated metallic fuel are within 3% each other.• show that four compositionally distinct zones exist comprising Zr.• Pu content across the pin diameter varies from a low approximately 8 wt.% to high 22 wt. %.• can quantify atoms lost or gained compositional zone.
Journal Article Micro- and Nano-Characterization of Neutron Irradiated TRISO Coated Particles Get access Isabella van Rooyen, Rooyen Fuel Design Development Department, Idaho National Laboratory, Falls, ID, USANuclear Engineering Program, Materials Science University Florida, Gainesville, FL, USA Corresponding author: Isabella.vanrooyen@inl.gov Search for other works by this author on: Oxford Academic Google Scholar Yong Yang, Yang Nuclear Karen Wright, Wright Post-Irradiation Examination...
Tristructural isotropic (TRISO) fuel particles are designed for use as in high temperature gas reactors.The AGR-1 concentrically layered design consisted of a 350 m diameter, 19.7% enrichment uranium oxide-carbide kernel the center, surrounded by layers porous carbon buffer layer (100 m), denser inner pyrolytic (IPyC) (40 SiC (35 and an outer (OPyC)(40 m) (Figure 1) [1].The TRISO is intended to keep fission products retained within particle.
Abstract Two similarly-irradiated TRISO nuclear fuel particles, one safety-tested and not-safety-tested, were examined by electron probe microanalysis (EPMA) as part of the advanced gas reactor (AGR) development qualification programme. The primary objective this study was to determine effect high temperature safety testing on fission product quantification distribution. Concentration profiles for products collected along two radii in each particle. Fission mass balance distribution both...