Dong-Jin Euh - Concepedia

Author

Dong-Jin Euh

Korea Atomic Energy Research Institute

Also Known As

D. J. Euh, D.J. EUH, D.J. Euh, Dong-Jin EUH, Dong-Jin Euh, Dongjin EUH, Dongjin Euh

106

Publications

992

Citations

H-Index

Concepts

All Affiliations

Korea Atomic Energy Research Institute Seoul National University Korea University of Science and Technology Pusan National University Purdue University West Lafayette

About

Dong-Jin Euh is an author at Korea Atomic Energy Research Institute specializing in engineering, multiphase flow, and fluid mechanics.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	20	31	789
2	Civil Engineering	5	5	131
3	Education	2	2	47
4	Applied Physics	2	2	43
5	Biostatistics	1	1	14

Dong-Jin Euh

Publications

867

Citations

H-Index

Page 1

	Year	Citations
Modeling of bubble coalescence and break-up considering turbulent suppression phenomena in bubbly two-phase flow Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, International Journal of Multiphase Flow Unsteady FlowBubble DynamicEngineeringFluid MechanicsTurbulence	2013	72
Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus Byongjo Yun, Byoung-Uhn Bae, Dong-Jin Euh, Nuclear Engineering and Design Cavitating FlowBubble DynamicEngineeringHydrodynamic CavitationMixed Convection	2009	51
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
Characteristics of Bubble Departure Frequency in a Low-Pressure Subcooled Boiling Flow Dong-Jin Euh, Basar Ozar, Takashi Hibiki, Journal of Nuclear Science and Technology AeroacousticsEfficient MethodologyBubble Departure FrequencyEngineeringBubble Dynamic	2010	48
Scaling for the ECC bypass phenomena during the LBLOCA reflood phase Byongjo Yun, Hyoung Kyu Cho, Dong-Jin Euh, Nuclear Engineering and Design	2004	44
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor Seok-Kyu Chang, Dong-Jin Euh, Hae Seob Choi, Nuclear Engineering and Technology EngineeringSingle-phase FlowFluid MechanicsMechanical EngineeringPressure Loss	2016	43
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
Development of the five-sensor conductivity probe method for the measurement of the interfacial area concentration Dong-Jin Euh, Byongjo Yun, Chul-Hwa Song, Nuclear Engineering and Design Sensor TechnologyElectrical EngineeringEngineeringSensorsMeasurement	2001	33
A new method of relating a chord length distribution to a bubble size distribution for vertical bubbly flows Nhan Hien Hoang, Dong-Jin Euh, Byongjo Yun, International Journal of Multiphase Flow AeroacousticsUnsteady FlowBubble DynamicEngineeringFluid Mechanics	2015	30
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

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