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Daeseong Jo
Daeseong Jo
Associate Professor, School of Mechanical Engineering, Kyungpook National University
Verified email at knu.ac.kr - Homepage
Title
Cited by
Cited by
Year
Experimental investigation of convective heat transfer in a narrow rectangular channel for upward and downward flows
D Jo, OS Al-Yahia, A RAGA'I M, J Park, H Chae
Nuclear Engineering and Technology 46 (2), 195-206, 2014
582014
ONB, OSV, and OFI for subcooled flow boiling through a narrow rectangular channel heated on one-side
OS Al-Yahia, D Jo
International Journal of Heat and Mass Transfer 116, 136-151, 2018
452018
Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channel
OS Al-Yahia, D Jo
Annals of Nuclear Energy 109, 30-40, 2017
402017
Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors
D Jo, J Park, H Chae
Progress in Nuclear Energy 71, 39-51, 2014
392014
Effect of coalescence and breakup on bubble size distributions in a two-dimensional packed bed
D Jo, ST Revankar
Chemical engineering science 65 (14), 4231-4238, 2010
382010
Cost–benefit analysis of BeO–UO2 nuclear fuel
SK Kim, WI Ko, HD Kim, ST Revankar, W Zhou, D Jo
Progress in Nuclear Energy 52 (8), 813-821, 2010
312010
Investigation of bubble breakup and coalescence in a packed-bed reactor–Part 1: A comparative study of bubble breakup and coalescence models
D Jo, ST Revankar
International Journal of Multiphase Flow 37 (9), 995-1002, 2011
282011
Bubble mechanisms and characteristics at pore scale in a packed-bed reactor
D Jo, ST Revankar
Chemical engineering science 64 (13), 3179-3187, 2009
282009
Experimental studies of condensing vapor bubbles in subcooled pool water using visual and acoustic analysis methods
H Jo, D Jo
Annals of Nuclear Energy 110, 171-185, 2017
272017
The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel
J Lee, D Jo, H Chae, SH Chang, YH Jeong, JJ Jeong
Experimental Thermal and Fluid Science 69, 86-98, 2015
212015
Transient thermal hydraulic analysis of the IAEA 10 MW MTR reactor during Loss of Flow Accident to investigate the flow inversion
OS AL-Yahia, MA Albati, J Park, H Chae, D Jo
Annals of Nuclear Energy 62, 144-152, 2013
192013
Investigation of bubble breakup and coalescence in a packed-bed reactor–Part 2: Development of a new bubble breakup and coalescence model
D Jo, ST Revankar
International journal of multiphase flow 37 (9), 1003-1012, 2011
192011
Surface orientation effects on bubble behaviors and critical heat flux mechanism in saturated water pool
EF Tanjung, D Jo
International Journal of Heat and Mass Transfer 133, 179-191, 2019
172019
Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP
MA Albati, OS AL-Yahia, J Park, H Chae, D Jo
Progress in Nuclear Energy 71, 1-8, 2014
172014
Experimental study on the Onset of Nucleate Boiling in a narrow rectangular channel under transversely non-uniform and uniform heating
T Kim, OS Al-Yahia, D Jo
Experimental Thermal and Fluid Science 99, 158-168, 2018
162018
Experimental study of bubble behaviors and CHF on printed circuit board (PCB) in saturated pool water at various inclination angles
EF Tanjung, BO Alunda, YJ Lee, D Jo
Nuclear Engineering and Technology 50 (7), 1068-1078, 2018
162018
Flow Instability (FI) for subcooled flow boiling through a narrow rectangular channel under transversely uniform and non-uniform heat flux
OS Al-Yahia, T Kim, D Jo
International Journal of Heat and Mass Transfer 125, 116-128, 2018
142018
Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production
D Jo, KH Lee, HC Kim, H Chae
Annals of Nuclear Energy 71, 467-474, 2014
142014
Effects of transverse power distribution on thermal hydraulic analysis
D Jo, CG Seo
Progress in Nuclear Energy 81, 16-21, 2015
132015
Effect of transverse power distribution on the ONB location in the subcooled boiling flow
OS Al-Yahia, YJ Lee, D Jo
Annals of Nuclear Energy 100, 98-106, 2017
112017
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