Search Results - "Cho, Hyoung-Kyu" :: K.UTB vyhledávací portál

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Multi-scale simulation of wall film condensation in the presence of non-condensable gases using heat structure-coupled CFD and system analysis codes

by Lee, Chang Won, Yoo, Jin-Seong, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (2021)

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Experimental investigation and CFD analysis on cross flow in the core of PMR200

by Lee, Jeong-Hun, Yoon, Su-Jong, Cho, Hyoung-Kyu, Jae, Moosung, Park, Goon-Cherl
Published in Annals of nuclear energy (01.09.2015)

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Investigation on emergency core coolant bypass with local measurement of liquid film thickness using electrical conductance sensor fabricated on flexible printed circuit board

by Choi, Chi-Jin, Cho, Hyoung Kyu
Published in International journal of heat and mass transfer (01.08.2019)

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Verification and improvement of dynamic motion model in MARS for marine reactor thermal-hydraulic analysis under ocean condition

by Beom, Hee-Kwan, Kim, Geon-Woo, Park, Goon-Cherl, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (2019)

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Application of CUPID for subchannel-scale thermal-hydraulic analysis of pressurized water reactor core under single-phase conditions

by Yoon, Seok Jong, Kim, Seul Been, Park, Goon Cherl, Yoon, Han Young, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (2018)

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Investigation of equivalent spherical bubble diameter at high inlet velocity pool scrubbing conditions

by Bicer, Erol, Hong, Soon-Joon, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (01.10.2024)

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IMPROVEMENT OF CUPID CODE FOR SIMULATING FILMWISE STEAM CONDENSATION IN THE PRESENCE OF NONCONDENSABLE GASES

by LEE, JEHEE, PARK, GOON-CHERL, CHO, HYOUNG KYU
Published in Nuclear engineering and technology (2015)

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Three-dimensional looped network analysis code including core thermal analysis model for prismatic very high temperature gas-cooled reactor

by Lee, Jeong-Hun, Cho, Hyoung Kyu, Park, Goon-Cherl
Published in International journal of thermal sciences (01.09.2019)

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Multiphysics analysis of heat pipe cooled microreactor core with adjusted heat sink temperature for thermal stress reduction using OpenFOAM coupled with neutronics and heat pipe code

by Jeong, Myung Jin, Im, Jaeuk, Lee, San, Cho, Hyoung Kyu
Published in Frontiers in energy research (05.06.2023)

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Assessment of MARS-KS prediction capability for natural circulation flow in passive heat removal system

by Lee, Jehee, Park, Youngjae, Jeon, Seong-Su, Park, Ju-Yeop, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (01.08.2024)

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Numerical Investigations of Liquid Film Offtake by Transverse Gas Flow in a Downcomer Annulus Geometry

by Choi, Chi-Jin, Cho, Hyoung Kyu
Published in Frontiers in energy research (16.03.2022)

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Multi-scale simulation of wall film condensation in the presence of non-condensable gases using heat structure-coupled CFD and system analysis codes

by Lee, Chang Won, Yoo, Jin-Seong, Cho, Hyoung Kyu
Published in Nuclear engineering and technology (01.08.2021)

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Development of wall and interfacial friction models for two-dimensional film flow with local measurement methods

by Yang, Jin-Hwa, Euh, Dong-Jin, Cho, Hyoung-Kyu, Park, Goon-Cherl
Published in Nuclear engineering and design (01.09.2018)

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Feasibility Test of a Liquid Film Thickness Sensor on a Flexible Printed Circuit Board Using a Three-Electrode Conductance Method

by Lee, Kyu Byung, Kim, Jong Rok, Park, Goon Cherl, Cho, Hyoung Kyu
Published in Sensors (Basel, Switzerland) (27.12.2016)

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Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS

by Seo, Hyungjoo, Choi, Moon Hee, Park, Sang Wook, Kim, Geon Woo, Cho, Hyoung Kyu, Chung, Bub Dong
Published in Nuclear engineering and technology (01.11.2022)

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Heat structure coupling of CUPID and MARS for the multi-scale simulation of the passive auxiliary feedwater system

by Kyu Cho, Hyoung, Cho, Yun Je, Yoon, Han Young
Published in Nuclear engineering and design (01.07.2014)

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Development of the loss coefficient correlation for cross flow between graphite fuel blocks in the core of prismatic very high temperature reactor-PMR200

by Lee, Jeong-Hun, Cho, Hyoung-Kyu, Park, Goon-Cherl
Published in Nuclear engineering and design (01.10.2016)

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Jet impingement model for system analysis code to enhance mixing behavior prediction in downcomer during DVI line break accident

by Lee, Keo Hyoung, Kim, Sin Yeob, Cho, Hyoung Kyu, Park, Goon Cherl
Published in Nuclear engineering and design (01.08.2018)

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Prediction of nucleate boiling heat transfer on horizontal U-shaped heat exchanger submerged in a pool of water using MARS code

by Jeon, Seong-Su, Hong, Soon-Joon, Cho, Hyoung-Kyu, Park, Goon-Cherl
Published in Nuclear engineering and design (15.12.2015)

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

by Yang, Jin-Hwa, Cho, Hyoung-Kyu, Kim, Seok, Euh, Dong-Jin, Park, Goon-Cherl
Published in Nuclear engineering and design (01.12.2015)

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