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Dong-Jin Euh

Observed names: D. J. Euh, D.J. EUH, D.J. Euh, Dong Jin Euh, Dong-Jin EUH, Dongjin EUH, Dongjin Euh, Euh Dong-Jin
ORCID: 0009-0007-8120-4388
Observed ORCID: 0009-0007-8120-4388
OpenAlex ID: A5111635986
An application of the wavelet analysis technique for the objective discrimination of two-phase flow patterns
2010 · Van Thai Nguyen, Dong Jin Euh, et al. · International Journal of Multiphase Flow · 79
Modeling of bubble coalescence and break-up considering turbulent suppression phenomena in bubbly two-phase flow
2013 · Van Thai Nguyen, Chul-Hwa Song, et al. · International Journal of Multiphase Flow · 76
Observation of critical heat flux mechanism in horizontal pool boiling of saturated water
2014 · In-Cheol Chu, Hee Cheon NO, et al. · Nuclear Engineering and Design · 58
Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus
2009 · B.J. Yun, B.U. Bae, et al. · Nuclear Engineering and Design · 55
A mechanistic model for predicting the maximum diameter of vapor bubbles in a subcooled boiling flow
2015 · Nhan Hien Hoang, In-Cheol Chu, et al. · International Journal of Heat and Mass Transfer · 52
Characteristics of Bubble Departure Frequency in a Low-Pressure Subcooled Boiling Flow
2010 · Dongjin EUH, Basar OZAR, et al. · Journal of Nuclear Science and Technology · 48
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Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
2016 · Seok-Kyu Chang, Dong-Jin Euh, et al. · Nuclear Engineering and Technology · 45
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Scaling for the ECC bypass phenomena during the LBLOCA reflood phase
2004 · B.J. Yun, H.K. Cho, et al. · Nuclear Engineering and Design · 45
A bubble dynamics-based model for wall heat flux partitioning during nucleate flow boiling
2017 · Nhan Hien Hoang, Chul-Hwa Song, et al. · International Journal of Heat and Mass Transfer · 43
Experimental evaluation of local bubble parameters of subcooled boiling flow in a pressurized vertical annulus channel
2016 · In-Cheol Chu, Seung-Jun Lee, et al. · Nuclear Engineering and Design · 34
A new method of relating a chord length distribution to a bubble size distribution for vertical bubbly flows
2015 · N.H. Hoang, D.J. Euh, et al. · International Journal of Multiphase Flow · 33
Development of the five-sensor conductivity probe method for the measurement of the interfacial area concentration
2001 · D.J. Euh, B.J. Yun, et al. · Nuclear Engineering and Design · 32
Mechanism study of departure of nucleate boiling on forced convective channel flow boiling
2018 · Seol Ha Kim, In Cheol Chu, et al. · International Journal of Heat and Mass Transfer · 30
Experimental investigation of local two-phase flow parameters of a subcooled boiling flow in an annulus
2010 · Byong-Jo Yun, Byoung-Uhn Bae, et al. · Nuclear Engineering and Design · 28
Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus during LBLOCA Reflood Phase with a Direct Vessel Injection Mode
2003 · Tae-Soon Kwon, Byong-Jo Yun, et al. · Nuclear Technology · 27
Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents
2006 · Ki Yong Choi, Hyun Sik Park, et al. · Nuclear Technology · 26
Contribution of thermal–hydraulic validation tests to the standard design approval of SMART
2017 · Hyun-Sik Park, Tae-Soon Kwon, et al. · Nuclear Engineering and Technology · 24
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Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400
2008 · B.J. Yun, D.J. Euh, et al. · Nuclear Engineering and Design · 24
Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactor
2015 · Hyungmo Kim, Hwang Bae, et al. · Annals of Nuclear Energy · 23
Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method
2017 · Seok-Kyu Chang, Dong-Jin Euh, et al. · Annals of Nuclear Energy · 22
Experimental study on two-dimensional film flow with local measurement methods
2015 · Jin-Hwa Yang, Hyoung-Kyu Cho, et al. · Nuclear Engineering and Design · 22
Experimental study of the APR+ reactor core flow and pressure distributions under 4-pump running conditions
2013 · Kihwan Kim, Dong-Jin Euh, et al. · Nuclear Engineering and Design · 22
A Flow and Pressure Distribution of Apr+ Reactor Under the 4-pump Running Conditions With a Balanced Flow Rate
2012 · D.J. Euh, K.H. Kim, et al. · Nuclear Engineering and Technology · 22
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Computational Analysis of a Subcooled Boiling Flow with a One-group Interfacial Area Transport Equation
2008 · Byoung-Uhn BAE, Han-Young YOON, et al. · Journal of Nuclear Science and Technology · 22
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Mechanistic study for the interfacial area transport phenomena in an air/water flow condition by using fine-size bubble group model
2006 · B.G. Huh, D.J. Euh, et al. · International Journal of Heat and Mass Transfer · 21
Works count: 116
Citation count: 1,249
H-index: 22
I10-index: 40
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