A5101816180- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Heat Transfer and Boiling Studies
- Heat Transfer and Optimization
- Heat transfer and supercritical fluids
- Combustion and flame dynamics
- Advanced Combustion Engine Technologies
- Nuclear and radioactivity studies
- Spacecraft and Cryogenic Technologies
- Cyclone Separators and Fluid Dynamics
- Thermodynamic and Structural Properties of Metals and Alloys
- Combustion and Detonation Processes
- Heat Transfer Mechanisms
- Catalytic Processes in Materials Science
- Graphite, nuclear technology, radiation studies
- Radiative Heat Transfer Studies
- Nanofluid Flow and Heat Transfer
- Superconducting Materials and Applications
- Advanced Sensor Technologies Research
- Metallurgical Processes and Thermodynamics
- Probabilistic and Robust Engineering Design
- Flow Measurement and Analysis
- Advanced materials and composites
- Magnetic confinement fusion research
Idaho National Laboratory
2022-2024
Knoxville College
2021-2023
University of Tennessee at Knoxville
2020-2023
Ulsan National Institute of Science and Technology
2012-2021
Korea Atomic Energy Research Institute
2014-2021
Korea Electric Power Corporation (South Korea)
2008-2012
Pennsylvania State University
1998-2000
Nucleate boiling is an effective heat transfer method in power generation systems and cooling devices. In this letter, hybrid graphene/single-walled carbon nanotube (SWCNT), graphene, SWCNT films deposited on indium tin oxide (ITO) surfaces were fabricated to investigate the enhancement of nucleate phenomena described by critical flux coefficient. The graphene grown Cu foils transferred ITO surfaces. Furthermore, SWCNTs layer fabricate graphene/SWCNT films. We determined that film surface...
In this study, R-123 flow boiling experiments were carried out to investigate the effects of nanoparticle deposition on heater surfaces critical heat flux (CHF) and transfer. It is known that CHF enhancement by nanoparticles results from porous structures are very similar layers Chalk River unidentified deposit formed nuclear fuel rod during reactor operation period. Although previous studies have investigated surface through modifications, most limited pool conditions, therefore, transfer...
This paper presents a preliminary design and performance analysis of supercritical CO2 (SCO2) heat exchanger for an SCO2 power generation system. The purpose designing is to provide high-temperature high-pressure exchange core technology advanced systems. target outlet temperature pressure the were 600 °C 200 bar, respectively. A tubular type with staggered tube bundle was selected as exchanger, liquefied petroleum gas (LPG) air sources. based on material selection available specification....
Recently, molten salt has received attention as a promising coolant for advanced nuclear reactors, especially fluoride salt-cooled high-temperature reactor. The heat transfer characteristics of provide great advantages application primary coolant, because its superior performance in terms sustainability, economics, safety, and reliability compared with gas coolant. However, understanding the thermal-hydraulic salts by experimental method is difficult corrosion toxicity issue. Therefore, oil...