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Chang, Soon Heung (장순흥)
명예교수, (원자력및양자공학과)

http://esdas.kaist.ac.kr

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에너지시스템설계
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    NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
    1
    Flow boiling CHF experiment with sudden expansion tubes

    Kim, Yong Jin; Song, Sub Lee; Moon, Sang-Ki; et al, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.114, 2020-05

    2
    Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure

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

    3
    Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion

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

    4
    Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels

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

    5
    The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel

    Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; et al, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.69, pp.86 - 98, 2015-12

    6
    Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels

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

    7
    A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA

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

    8
    A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel

    Choi, Gil Sik; Jeong, Yong Hoon; Chang, Soon Heung, NUCLEAR ENGINEERING AND DESIGN, v.294, pp.103 - 116, 2015-12

    9
    An experimental study on CHF enhancement of wire nets covered surface in R-134a flow boiling under high pressure and high mass flux conditions

    Song, Sub Lee; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.90, pp.761 - 768, 2015-11

    10
    INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.6, pp.678 - 699, 2015-10

    11
    Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident

    Kim, Sang Ho; Futami, Tsuneo; Chang, Soon-Heung; et al, SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, v.520756, 2015-02

    12
    The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure

    Kang, Dong Gu; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.275, pp.142 - 153, 2014-08

    13
    Fusion Licensing and Safety Studies in Korea

    Kim, Hyuck Jong; Kim, Hyung Chan; Kwon, Myeun; et al, IEEE TRANSACTIONS ON PLASMA SCIENCE, v.42, no.3, pp.664 - 670, 2014-03

    14
    CHF enhancement of SiC nanofluid in pool boiling experiment

    Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.52, pp.12 - 18, 2014-01

    15
    Flow instability during subcooled boiling for a downward flow at low pressure in a vertical narrow rectangular channel

    Lee, Juhyung; Chae, Heetaek; Chang, Soon Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.67, pp.1170 - 1180, 2013-12

    16
    Development of an environmental radiation analysis research capability in the UAE

    Kim, Sung-yeop; Kim, Chankyu; Lee, Kun Jai; et al, APPLIED RADIATION AND ISOTOPES, v.81, pp.190 - 195, 2013-11

    17
    Development of safety analysis methodology for moderator system failure of CANDU-6 reactor by thermal-hydraulics/physics coupling

    Kim, Jong Hyun; Jin, Dong Sik; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.263, pp.241 - 254, 2013-10

    18
    Analysis of economics and safety to cope with station blackout in PWR

    Al Shehhi, Ahmed Saeed; Chang, Soon-Heung; Kim, Sang Ho; et al, ANNALS OF NUCLEAR ENERGY, v.59, pp.63 - 71, 2013-09

    19
    Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    Chang, Soon-Heung; Kim, Sang Ho; Choi, Jae Young, NUCLEAR ENGINEERING AND DESIGN, v.260, pp.104 - 120, 2013-07

    20
    A combined deterministic and probabilistic procedure for safety assessment of beyond design basis accidents in nuclear power plant: Application to ECCS performance assessment for design basis LOCA redefinition

    Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.260, pp.165 - 174, 2013-07
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