Researcher Page

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Jeong, Yong Hoon (정용훈)
부교수, Department of Nuclear and Quantum Engineering(원자력및양자공학과)
Research Area
nuclear system design and safety analysis, nuclear hydrogen, desalination, electric vehicle, power transport system
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    NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
    1
    Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials

    Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, ANNALS OF NUCLEAR ENERGY, v.136, 2020-02

    2
    Effects of silica nanoparticles and low concentration on the deterioration of critical heat flux in a pool boiling experiment with a flat-type heater

    Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.144, 2019-12

    3
    Assessment of advanced RANS models ability to predict a turbulent swept liquid metal flow over a wire in a channel

    You, Byung-Hyun; Jeong, Yong Hoonresearcher; Addad, Yacine, NUCLEAR ENGINEERING AND DESIGN, v.353, 2019-11

    4
    Effect of dimensions and downward-facing angle on CHF under atmospheric condition

    Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.102, pp.603 - 610, 2019-04

    5
    CHF correlation development under ERVC conditions by using the local liquid velocity from PIV measurements

    Yoon, Jongwoong; Kam, Dong Hoon; Park, Hae Min; et al, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.128, pp.171 - 184, 2019-01

    6
    CHF experiment with downward-facing carbon and stainless steel plates under pressurized conditions

    Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.125, pp.670 - 680, 2018-10

    7
    Critical heat flux model on a downward facing surface for application to the IVR conditions

    Park, Hae Min; Jeong, Yong Hoonresearcher; Carnevali, Sofia, NUCLEAR ENGINEERING AND DESIGN, v.330, pp.317 - 324, 2018-04

    8
    Flow boiling CHF enhancement by wettability and flow conditions in a slug flow in the rectangular curved channel

    Park, Hae Min; Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.91, pp.388 - 398, 2018-02

    9
    Critical heat flux on downward-facing carbon steel flat plates under atmospheric condition

    Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.90, pp.22 - 27, 2018-01

    10
    Fluid-to-fluid scaling criteria development for modeling high pressure steam condensation in horizontal tubes

    Khasawneh, Khalid; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.116, pp.1266 - 1281, 2018-01

    11
    Safety evaluation of supercritical CO2 cooled micro modular reactor

    Oh, Bong Seong; Ahn, Yoon Han; Yu, Hwanyeal; et al, ANNALS OF NUCLEAR ENERGY, v.110, pp.1202 - 1216, 2017-12

    12
    Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure

    Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heungresearcher; et al, ANNALS OF NUCLEAR ENERGY, v.109, pp.498 - 506, 2017-11

    13
    Analysis of CHF enhancement by magnetite nanoparticle deposition in the subcooled flow boiling region

    Choi, Young Jae; Kam, Dong Hoon; Jeong, Yong Hoonresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.109, pp.1191 - 1199, 2017-06

    14
    Improving power and desalination capabilities of a large nuclear power plant with supercritical CO2 power technology

    Lee, Won Woong; Bae, Seong Jun; Jung, Yong Hun; et al, DESALINATION, v.409, pp.136 - 145, 2017-05

    15
    A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region

    Kim, Seong Gu; Yu, HwanYeal; Moon, Jangsik; et al, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.41, no.4, pp.512 - 525, 2017-03

    16
    Development of analytical model for solar chimney power plant with and without water storage system

    Choi, Young Jae; Kam, Dong Hoon; Park, Yoon Won; et al, ENERGY, v.112, pp.200 - 207, 2016-10

    17
    Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yongheeresearcher; et al, PROGRESS IN NUCLEAR ENERGY, v.91, pp.183 - 207, 2016-08

    18
    Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels

    Choi, Gil Sik; Chang, Soon Heungresearcher; Jeong, Yong Hoonresearcher, NUCLEAR ENGINEERING AND DESIGN, v.303, pp.1 - 16, 2016-07

    19
    A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA

    Kim, Sang Ho; Chang, Soon Heungresearcher; Choi, Yu Jung; et al, NUCLEAR ENGINEERING AND DESIGN, v.295, pp.346 - 359, 2015-12

    20
    Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels

    Choi, Gil Sik; Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, Transactions of the Korean Society of Mechanical Engineers, v.39, no.12, pp.953 - 963, 2015-12

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