Jo Jo Lee

ORCID: 0000-0001-5956-0422
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Graphite, nuclear technology, radiation studies
  • Nuclear and radioactivity studies
  • Advanced ceramic materials synthesis
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Radiation Shielding Materials Analysis
  • Silicon Carbide Semiconductor Technologies
  • Material Properties and Applications
  • Advanced materials and composites
  • Silicon and Solar Cell Technologies
  • Metallurgical Processes and Thermodynamics
  • Fusion materials and technologies
  • Advanced Aircraft Design and Technologies
  • Semiconductor materials and devices
  • Solar Radiation and Photovoltaics
  • Aluminum Alloys Composites Properties
  • Intermetallics and Advanced Alloy Properties
  • Nuclear materials and radiation effects
  • Photovoltaic System Optimization Techniques
  • Iron and Steelmaking Processes
  • Recycling and utilization of industrial and municipal waste in materials production

Government of the United States of America
2023

Oak Ridge National Laboratory
2015-2023

Hong Kong Polytechnic University
2021

University of Missouri
2013-2020

Institute for Nuclear Science and Technology
2020

Having an exciting array of applications, the scope unmanned aerial vehicle (UAV) application could be far wider one if its flight endurance can prolonged. Solar-powered UAV, promising notable prolongation in endurance, is drawing increasing attention industries’ recent research and development. This work arose from a Bachelor’s degree capstone project at Hong Kong Polytechnic University. The aims to modify 2-metre wingspan remote-controlled (RC) UAV available consumer market powered by...

10.3390/drones5020044 article EN cc-by Drones 2021-05-24

10.1016/j.jnucmat.2017.11.053 article EN publisher-specific-oa Journal of Nuclear Materials 2017-12-14

Chemical vapor deposited SiC single crystal and polycrystals were exposed to a static beryllium-bearing molten fluoride salt, 2LiF–BeF2 for 500 1000 h at 750 °C. Overall, the polycrystalline materials experienced slight weight loss nominal surface etching regardless of material type. Localized pitting nonuniform Si removal from regions associated with trace metal impurities oxygen. Cross-sectional observation revealed minimal subsurface changes in microstructure. The corrosion damage...

10.2139/ssrn.4394516 article EN 2023-01-01

Abstract Thorium Fuel Cycle for a Molten Salt Reactor: State of Missouri Feasibility Study was uncovered long ago amongst the waste products several mining operations inthe state Missouri. Recently, feasibility using thorium as an alternative to uranium-based nuclear fuel is gaining global interest. Due potential security issues surrounding theuranium cycle and environmental concerns posed by fossil fuel-based power, there isrenewed interest in utilizing because its economy,natural abundance...

10.18260/1-2--23194 article EN 2020-09-04
Coming Soon ...