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

Authors: Erol Bicer, Soon-Joon Hong, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4307-4326 (2024)

Subject Terms: Pool scrubbing, Equivalent spherical diameter, IATE, Turbulent intensity, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573324002511; https://doaj.org/toc/1738-5733

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

Authors: Jehee Lee, Youngjae Park, Seong-Su Jeon, Ju-Yeop Park, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3435-3449 (2024)

Subject Terms: Passive safety system, Passive heat removal system, Natural circulation flow, Pressure drop, Two-phase flow, MARS-KS, Nuclear engineering. Atomic power, TK9001-9401

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Relation: http://www.sciencedirect.com/science/article/pii/S1738573324002109; https://doaj.org/toc/1738-5733

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

Authors: Hyungjoo Seo, Moon Hee Choi, Sang Wook Park, Geon Woo Kim, Hyoung Kyu Cho, Bub Dong Chung

Source: Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4373-4391 (2022)

Subject Terms: Marine reactor, System TH analysis code, MARS-KS moving reactor model, Multi-dimensional flow, Verification and validation, Nuclear engineering. Atomic power, TK9001-9401

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Relation: http://www.sciencedirect.com/science/article/pii/S1738573322003412; https://doaj.org/toc/1738-5733

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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

Authors: Myung Jin Jeong, Jaeuk Im, San Lee, Hyoung Kyu Cho

Source: Frontiers in Energy Research, Vol 11 (2023)

Subject Terms: microreactor, heat pipe, multiphysics analysis, thermal stress, OpenFOAM, PRAGMA, General Works

File Description: electronic resource

Relation: https://www.frontiersin.org/articles/10.3389/fenrg.2023.1213000/full; https://doaj.org/toc/2296-598X

Access URL: https://doaj.org/article/3bf79495886b49cc959fca632b29e8f8

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

Authors: Chang Won Lee, Jin-Seong Yoo, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2488-2498 (2021)

Subject Terms: CUPID, MARS, STAR-CCM+, Wall condensation, Non-condensable gas, Multi-scale code coupling, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573321001431; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/9cc73ece5445408f8db7c12b85829566

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

Authors: Chi-Jin Choi, Hyoung Kyu Cho

Source: Frontiers in Energy Research, Vol 10 (2022)

Subject Terms: volume-of-fluid-slip model, multi-regime, droplet diameter, interface turbulence damping, emergency core coolant bypass, General Works

File Description: electronic resource

Relation: https://www.frontiersin.org/articles/10.3389/fenrg.2022.847458/full; https://doaj.org/toc/2296-598X

Access URL: https://doaj.org/article/322a976195304ec8b29a286eab16da06

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

Authors: Hee-Kwan Beom, Geon-Woo Kim, Goon-Cherl Park, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 51, Iss 5, Pp 1231-1240 (2019)

Subject Terms: Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573318306855; https://doaj.org/toc/1738-5733

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

Authors: Seok Jong Yoon, Seul Been Kim, Goon Cherl Park, Han Young Yoon, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 50, Iss 1, Pp 54-67 (2018)

Subject Terms: Advanced Power Reactor 1400, CUPID, Reactor Core Thermal–Hydraulic Analysis, Subchannel-Scale Thermal–Hydraulic Analysis, Validation, Nuclear engineering. Atomic power, TK9001-9401

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Relation: http://www.sciencedirect.com/science/article/pii/S1738573317302632; https://doaj.org/toc/1738-5733

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Improvement of CUPID code for simulating filmwise steam condensation in the presence of noncondensable gases

Authors: Jehee Lee, Goon-Cherl Park, Hyoung Kyu Cho

Source: Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 567-578 (2015)

Subject Terms: CUPID, Large system, Liquid film, Noncondensable gas, Wall condensation, Wall function, Nuclear engineering. Atomic power, TK9001-9401

File Description: electronic resource

Relation: http://www.sciencedirect.com/science/article/pii/S1738573315001370; https://doaj.org/toc/1738-5733

Access URL: https://doaj.org/article/490e934cdd6548688e4c81c4f13b34c3

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

Authors: HAN YOUNG YOON, JAE RYONG LEE, HYUNGRAE KIM, IK KYU PARK, CHUL-HWA SONG, HYOUNG KYU CHO, JAE JUN JEONG

Source: Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 655-666 (2014)

Subject Terms: The CUPID Code, Domain Decomposition Parallel Method, Code Coupling Via Heat Structure, Steam Generator, Nuclear engineering. Atomic power, TK9001-9401

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Relation: http://www.sciencedirect.com/science/article/pii/S1738573315301054; https://doaj.org/toc/1738-5733

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

Authors: Kyu Byung Lee, Jong Rok Kim, Goon Cherl Park, Hyoung Kyu Cho

Source: Sensors, Vol 17, Iss 1, p 42 (2016)

Subject Terms: liquid film thickness, liquid film sensor, three electrode conductance method, two-phase flow experiment, Chemical technology, TP1-1185

File Description: electronic resource

Relation: http://www.mdpi.com/1424-8220/17/1/42; https://doaj.org/toc/1424-8220

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

Authors: Kyu Byung Lee, Jong Rok Kim, Goon Cherl Park, Hyoung Kyu Cho

Source: Sensors (14248220); Jan2017, Vol. 17 Issue 1, p42, 14p

Subject Terms: LIQUID films, PRINTED circuits, ELECTRODES, ELECTRIC admittance, THICKNESS measurement

Development of Heat Transfer Model Package for Horizontal U-Shaped Heat Exchanger Submerged in Pool of Passive Safety System.

Authors: Seong-Su Jeon, Soon-Joon Hong, Hyoung-Kyu Cho, Goon-Cherl Park

Source: Nuclear Technology; Nov2016, Vol. 196 Issue 2, p303-318, 16p

ANALYTICAL STUDY ON THE EFFECTIVE THERMAL CONDUCTIVITY OF VHTR FUEL BLOCK GEOMETRY WITH MULTIPLE CYLINDRICAL HOLES.

Authors: DONG-HO SHIN¹, SU-JONG YOON², TAK, NAM-IL³, PARK, GOON-CHERL¹, HYOUNG-KYU CHO¹, chohk@snu.ac.kr

Source: Nuclear Technology; Sep2015, Vol. 191 Issue 3, p213-222, 10p

PARAMETRIC SENSITIVITY STUDY ON THE REFLOODING MODELS OF THE MARS CODE BASED ON 6 x 6 ROD BUNDLE TEST RESULTS.

Authors: KI-YONG CHOI, SEOK CHO, HYOUNG-KYU CHO, CHUL-HWA SONG

Source: Nuclear Technology; Apr2010, Vol. 170 Issue 1, p54-67, 14p, 3 Diagrams, 2 Charts, 19 Graphs

Subject Terms: HYDRAULICS, FLOODS, HEAT flux, HEAT transfer, INLETS

ASSESSMENT OF MARS-GCR CODE FOR A NEW REACTOR CAVITY COOLING SYSTEM DESIGN.

Authors: Yun-je Cho¹ seni10@snu.ac.kr, Hyoung-kyu Cho², Goon-cherl Park¹

Source: Nuclear Technology. Apr2008, Vol. 162 Issue 1, p92-106. 15p. 7 Diagrams, 2 Charts, 13 Graphs.

Subject Terms: *COOLING, *HEAT radiation & absorption, *HEAT transfer, *NUCLEAR reactors, *TEMPERATURE, *ENERGY transfer

EXPERIMENTS ON A WATER POOL-TYPE REACTOR CAVITY COOLING SYSTEM IN A HIGH-TEMPERATURE GAS-COOLED REACTOR.

Authors: Hyoung Kyu Cho^1,2 hkcho@kaeri.re.kr, Yun Je Cho¹, Moon Oh Kim¹, Goon Cherl Park¹

Source: Nuclear Technology. Jul2007, Vol. 159 Issue 1, p39-58. 20p. 1 Black and White Photograph, 5 Diagrams, 2 Charts, 8 Graphs.

Subject Terms: *GAS cooled reactors, *PEBBLE bed reactors, *COOLING, *NUCLEAR reactor safety measures, *PROTOTYPES