In-Cheol Chu - Concepedia

Author

In-Cheol Chu

Korea Atomic Energy Research Institute

Also Known As

In-Cheol CHU, In-Cheol Chu, Incheol Chu

Publications

618

Citations

H-Index

Concepts

All Affiliations

Korea Atomic Energy Research Institute Korea Advanced Institute of Science and Technology Korea University of Science and Technology

About

In-Cheol Chu is an author at Korea Atomic Energy Research Institute specializing in engineering, multiphase flow, and heat transfer.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	12	13	506
2	Mechanical Engineering	4	4	136
3	Applied Physics	1	1	61
4	Mechanics	1	1	10
5	Physics	1	1	61

In-Cheol Chu

Publications

579

Citations

H-Index

Page 1

	Year	Citations
Visualization of boiling structure and critical heat flux phenomenon for a narrow heating surface in a horizontal pool of saturated water In-Cheol Chu, Hee Cheon No, Chul-Hwa Song International Journal of Heat and Mass Transfer Critical Heat FluxHeat Transfer ProcessEngineeringSaturated WaterBoiling Structure	2013	81
Bubble Lift-off Diameter and Nucleation Frequency in Vertical Subcooled Boiling Flow In-Cheol Chu, Hee Cheon No, Chul-Hwa Song Journal of Nuclear Science and Technology EngineeringFluid MechanicsMechanical EngineeringNucleation FrequencyGas-liquid Flow	2011	61
Observation of critical heat flux mechanism in horizontal pool boiling of saturated water In-Cheol Chu, Hee Cheon No, Chul-Hwa Song, Nuclear Engineering and Design Critical Heat FluxHeat Transfer ProcessEngineeringSaturated WaterThermodynamics	2014	56
A mechanistic model for predicting the maximum diameter of vapor bubbles in a subcooled boiling flow Nhan Hien Hoang, In-Cheol Chu, Dong-Jin Euh, International Journal of Heat and Mass Transfer Cavitating FlowBubble DynamicEngineeringHydrodynamic CavitationLiquid-liquid Flow	2015	50
A bubble dynamics-based model for wall heat flux partitioning during nucleate flow boiling Nhan Hien Hoang, Chul-Hwa Song, In-Cheol Chu, International Journal of Heat and Mass Transfer Critical Heat FluxHeat Transfer ProcessEngineeringBubble Dynamics-based ModelBubble Dynamic	2017	40
Flow-induced vibration of nuclear steam generator U-tubes in two-phase flow In-Cheol Chu, Heung June Chung, Seungtae Lee Nuclear Engineering and Design Unsteady FlowEngineeringFluid MechanicsMechanical EngineeringMultiphase Flow	2011	37
Development of passive flow controlling safety injection tank for APR1400 In-Cheol Chu, Chul-Hwa Song, Bong Hyun Cho, Nuclear Engineering and Design EngineeringSafety Injection TankReactor SafetySystems EngineeringPressure Vessel	2007	37
Local heat transfer during reflux condensation mode in a U-tube with and without noncondensible gases Kyungwon Lee, Hee Cheon No, In-Cheol Chu, International Journal of Heat and Mass Transfer Heat Transfer ProcessNoncondensible GasesEngineeringReflux Condensation ModeHeat Exchanger	2006	34
Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel In-Cheol Chu, Seungjun Lee, Young Jung Youn, Nuclear Engineering and Design Cavitating FlowBubble DynamicEngineeringExperimental EvaluationHydrodynamic Cavitation	2016	30
Air-Water Countercurrent Flow Limitation in a Horizontal Pipe Connected to an Inclined Riser Seong-Kwon Kang, In-Cheol Chu, Hee Cheon No, Nuclear Engineering and Technology	1999	29

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