Ran Kong

ORCID: 0000-0001-8974-605X
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About
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Research Areas
  • Fluid Dynamics and Mixing
  • Heat Transfer and Boiling Studies
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear reactor physics and engineering
  • Drilling and Well Engineering
  • Heat transfer and supercritical fluids
  • Flow Measurement and Analysis
  • Fluid Dynamics and Heat Transfer
  • Nuclear Materials and Properties
  • Minerals Flotation and Separation Techniques
  • Combustion and Detonation Processes
  • Magnetic confinement fusion research
  • Fire dynamics and safety research
  • Nuclear Physics and Applications
  • Cyclone Separators and Fluid Dynamics
  • Particle accelerators and beam dynamics
  • Advancements in Photolithography Techniques
  • Electronic Packaging and Soldering Technologies
  • Heat Transfer Mechanisms
  • Water Systems and Optimization
  • High-Energy Particle Collisions Research
  • Reservoir Engineering and Simulation Methods
  • Iterative Learning Control Systems
  • Computational Fluid Dynamics and Aerodynamics
  • Laser-Plasma Interactions and Diagnostics

Purdue University West Lafayette
2017-2023

Niowave (United States)
2023

Pennsylvania State University
2016-2017

Guizhou University
2012

10.1016/j.nucengdes.2016.06.016 article EN Nuclear Engineering and Design 2016-08-09

10.1016/j.nucengdes.2020.111019 article EN publisher-specific-oa Nuclear Engineering and Design 2021-01-13

Inclined two-phase flow geometries can be found in advanced nuclear reactor systems, such as the helical coil steam generators being considered for use current integral generator designs. While this geometry includes inclination and centrifugal effects coupled together on flow, there have been limited studies to separate these develop robust models. The majority of research is conducted vertical channels, with recent work a horizontal orientation inclined pipes. In work, experiments are an...

10.1080/00295450.2022.2160172 article EN Nuclear Technology 2023-02-16

10.1016/j.ijheatmasstransfer.2018.04.025 article EN International Journal of Heat and Mass Transfer 2018-04-20

10.1016/j.nucengdes.2019.110411 article EN Nuclear Engineering and Design 2019-11-04

The objective of the Versatile Test Reactor (VTR) is to enable testing advanced reactor fuels and materials in a fast spectrum neutron environment. Internal cartridge loop capabilities are being developed that will allow coolant be isolated from coolant. This approach various coolants investigated, thereby maximizing capability. A sodium capability by team includes Argonne National Laboratory (Argonne) as laboratory partner, Framatome Inc. industrial Purdue University along with...

10.1080/00295639.2022.2052552 article EN cc-by-nc-nd Nuclear Science and Engineering 2022-05-03

Abstract The current work performs air-water experiments in three different pipe sizes of 38 mm, 51mm, and 102 mm to investigate the frequencies plug slug bubbles horizontal flows. local four-sensor conductivity probe is used establish experimental data for large elongated bubbles. investigated conditions focus on a relatively high superficial liquid velocity region (1.0 m/s ≤ jf 4.0 m/s), where limited are available literature. gas (jg) ranges from 0.19 3.0 m/s. In total, 19 studied. To...

10.1115/icone28-63179 article EN 2021-08-04
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