Hyoung-Kyu Cho

Hyoung-Kyu Cho

Seoul National University

Associate Professor

Department of Nuclear Engineering

Research Area

  • #Mechanics
  • #Materials science
  • #Flow (psychology)
  • #Nuclear reactor
  • #Coolant
  • #Engineering
  • #Nuclear engineering
  • #Heat transfer
  • #Thermal hydraulics
  • #Mechanical engineering

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Related papers to
‘ Mechanics ‘ : 17

  • Experimental study on two-dimensional film flow with local measurement methods

    2015/12

    1.0 Impact Factor

    12 citations

    Jin-Hwa Yang, Hyoung Kyu Cho, Seok Kim, Dong-Jin Euh, Goon-Cherl Park

    DOI : 10.1016/J.NUCENGDES.2015.07.073

    • #Engineering
    • #Mechanics
    • #Simulation
    • #Flow (psychology)
    • #Coolant
    • #Nuclear reactor
    • #Nuclear reactor core
    • #Reactor pressure vessel
    • #Computational fluid dynamics
    • #Pitot tube
    • #Loss-of-coolant accident

All papers authored by
‘ Hyoung-Kyu Cho ’ : 33

  • RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

    2014/10
    NUCLEAR ENGINEERING AND TECHNOLOGY

    0.8 Impact Factor

    30 citations

    Han Young Yoon, Jae Ryong Lee, Hyungrae Kim, Ik Kyu Park, Chul-Hwa Song, Hyoung Kyu Cho, Jae Jun Jeong

    DOI : 10.5516/NET.02.2014.023

    • #Engineering
    • #Mechanical engineering
    • #Flow (psychology)
    • #Coupling
    • #Nuclear reactor
    • #Physical model
    • #Porous medium
    • #Boiler (power generation)
    • #Two-phase flow
    • #Domain decomposition methods

Related papers to
‘ Mechanics ‘ : 17

  • Experimental study on two-dimensional film flow with local measurement methods

    2015/12
    NUCLEAR ENGINEERING AND DESIGN

    1.0 Impact Factor

    12 citations

    Jin-Hwa Yang, Hyoung Kyu Cho, Seok Kim, Dong-Jin Euh, Goon-Cherl Park

    DOI : 10.1016/J.NUCENGDES.2015.07.073

    • #Engineering
    • #Mechanics
    • #Simulation
    • #Flow (psychology)
    • #Coolant
    • #Nuclear reactor
    • #Nuclear reactor core
    • #Reactor pressure vessel
    • #Computational fluid dynamics
    • #Pitot tube
    • #Loss-of-coolant accident
  • Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases

    2015/08
    NUCLEAR ENGINEERING AND TECHNOLOGY

    0.8 Impact Factor

    11 citations

    Jehee Lee, Goon-Cherl Park, Hyoung Kyu Cho

    DOI : 10.1016/J.NET.2015.03.007

    • #Engineering
    • #Mechanics
    • #Waste management
    • #Heat transfer
    • #Condensation
    • #Mass transfer
    • #Nuclear reactor
    • #Containment
    • #Boundary layer
    • #Liquid film
    • #Steam condensation

Get access to
Contact information

Log in

All papers authored by
‘ Hyoung-Kyu Cho ’ : 33

  • RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

    2014/10
    NUCLEAR ENGINEERING AND TECHNOLOGY

    0.8 Impact Factor

    30 citations

    Han Young Yoon, Jae Ryong Lee, Hyungrae Kim, Ik Kyu Park, Chul-Hwa Song, Hyoung Kyu Cho, Jae Jun Jeong

    DOI : 10.5516/NET.02.2014.023

    • #Engineering
    • #Mechanical engineering
    • #Flow (psychology)
    • #Coupling
    • #Nuclear reactor
    • #Physical model
    • #Porous medium
    • #Boiler (power generation)
    • #Two-phase flow
    • #Domain decomposition methods
  • Experimental study on two-dimensional film flow with local measurement methods

    2015/12
    NUCLEAR ENGINEERING AND DESIGN

    1.0 Impact Factor

    12 citations

    Jin-Hwa Yang, Hyoung Kyu Cho, Seok Kim, Dong-Jin Euh, Goon-Cherl Park

    DOI : 10.1016/J.NUCENGDES.2015.07.073

    • #Engineering
    • #Mechanics
    • #Simulation
    • #Flow (psychology)
    • #Coolant
    • #Nuclear reactor
    • #Nuclear reactor core
    • #Reactor pressure vessel
    • #Computational fluid dynamics
    • #Pitot tube
    • #Loss-of-coolant accident

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