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Daeseong Jo, Ph.D. - Publications

Affiliations: 
Nuclear Engineering Purdue University, West Lafayette, IN, United States 
Area:
Nuclear Engineering, Multi-phase Flow, Fuel cell, Heat transfer
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33 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2021 Park J, Park I, Jo D. Statistical method for determining the onset of nucleate boiling under forced and natural convections in a rectangular channel Annals of Nuclear Energy. 150: 107863. DOI: 10.1016/J.Anucene.2020.107863  0.329
2020 Al-Yahia OS, Yoon HJ, Jo D. Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution Nuclear Engineering and Technology. DOI: 10.1016/J.Net.2020.05.025  0.433
2020 Tanjung EF, Albdour SA, Jeong YU, Jo D. Critical heat flux (CHF) in pool boiling under static and rolling conditions Nuclear Engineering and Technology. 52: 520-529. DOI: 10.1016/J.Net.2019.08.005  0.327
2020 Tanjung EF, Jo D. Visualization study on pool boiling critical heat flux under rolling motion International Journal of Heat and Mass Transfer. 153: 119620. DOI: 10.1016/J.Ijheatmasstransfer.2020.119620  0.34
2019 Al-Yahia OS, Yoon HJ, Jo D. Bubble dynamic parameters during subcooled flow boiling under uniform and non-uniform transverse heat distribution International Journal of Heat and Mass Transfer. 143: 118508. DOI: 10.1016/J.Ijheatmasstransfer.2019.118508  0.454
2019 Tanjung EF, Jo D. Surface orientation effects on bubble behaviors and critical heat flux mechanism in saturated water pool International Journal of Heat and Mass Transfer. 133: 179-191. DOI: 10.1016/J.Ijheatmasstransfer.2018.12.113  0.318
2018 Tanjung EF, Alunda BO, Lee YJ, Jo D. Experimental study of bubble behaviors and CHF on printed circuit board (PCB) in saturated pool water at various inclination angles Nuclear Engineering and Technology. 50: 1068-1078. DOI: 10.1016/J.Net.2018.06.011  0.302
2018 Al-Yahia OS, Kim T, Jo D. Flow Instability (FI) for subcooled flow boiling through a narrow rectangular channel under transversely uniform and non-uniform heat flux International Journal of Heat and Mass Transfer. 125: 116-128. DOI: 10.1016/J.Ijheatmasstransfer.2018.04.077  0.42
2018 Al-Yahia OS, Jo D. ONB, OSV, and OFI for subcooled flow boiling through a narrow rectangular channel heated on one-side International Journal of Heat and Mass Transfer. 116: 136-151. DOI: 10.1016/J.Ijheatmasstransfer.2017.09.011  0.411
2018 Kim T, Al-Yahia OS, Jo D. Experimental study on the Onset of Nucleate Boiling in a narrow rectangular channel under transversely non-uniform and uniform heating Experimental Thermal and Fluid Science. 99: 158-168. DOI: 10.1016/J.Expthermflusci.2018.07.036  0.339
2018 Kim T, Song YJ, Al-Yahia OS, Jo D. Prediction of the minimum point of the pressure drop in a narrow rectangular channel under a transversely non-uniform heat flux Annals of Nuclear Energy. 122: 163-174. DOI: 10.1016/J.Anucene.2018.08.046  0.382
2017 Jo H, Jo D. Experimental studies of condensing vapor bubbles in subcooled pool water using visual and acoustic analysis methods Annals of Nuclear Energy. 110: 171-185. DOI: 10.1016/J.Anucene.2017.06.030  0.351
2017 Al-Yahia OS, Jo D. Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channel Annals of Nuclear Energy. 109: 30-40. DOI: 10.1016/J.Anucene.2017.05.014  0.41
2017 Al-Yahia OS, Lee YJ, Jo D. Effect of transverse power distribution on the ONB location in the subcooled boiling flow Annals of Nuclear Energy. 100: 98-106. DOI: 10.1016/J.Anucene.2016.09.023  0.371
2016 Lee KY, Tahk YW, Jo D. Effect of oxide layer growth on fuel temperature of mini fuel plates Progress in Nuclear Energy. 91: 153-158. DOI: 10.1016/J.Pnucene.2016.04.013  0.302
2016 Kim KO, Park CJ, Jo D. A new strategy to select axial power distribution for thermal hydraulic analysis Annals of Nuclear Energy. 88: 265-271. DOI: 10.1016/J.Anucene.2015.11.010  0.303
2016 Al-Yahia OS, Lee H, Jo D. Transient analyses of the Jordanian 5 MW research reactor under LOEP accident Annals of Nuclear Energy. 87: 575-583. DOI: 10.1016/J.Anucene.2015.10.021  0.369
2016 Jo D. Hydrodynamic model of interfacial area for trickling flow in a packed bed Journal of Mechanical Science and Technology. 30: 171-178. DOI: 10.1007/S12206-015-1220-9  0.363
2015 Kim KO, Park S, Jo D. Transient behaviors of heavy water reflector system during postulated initiating events (PIEs) Progress in Nuclear Energy. 83: 144-151. DOI: 10.1016/J.Pnucene.2015.03.016  0.303
2015 Jo D, Seo CG. Effects of transverse power distribution on thermal hydraulic analysis Progress in Nuclear Energy. 81: 16-21. DOI: 10.1016/J.Pnucene.2014.12.017  0.34
2015 Lee J, Jo D, Chae H, Chang SH, Jeong YH, Jeong JJ. The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel Experimental Thermal and Fluid Science. 69: 86-98. DOI: 10.1016/J.Expthermflusci.2015.07.015  0.395
2015 Kim KO, Jo D. Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII Annals of Nuclear Energy. DOI: 10.1016/J.Anucene.2015.07.021  0.311
2015 Jo D, Kim H. Safety assessment of U-Mo fuel mini plates irradiated in HANARO reactor Annals of Nuclear Energy. 81: 219-226. DOI: 10.1016/J.Anucene.2015.02.042  0.387
2014 Jo D, Park J, Chae H. Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors Progress in Nuclear Energy. 71: 39-51. DOI: 10.1016/J.Pnucene.2013.11.006  0.389
2014 Albati MA, Al-Yahia OS, Park J, Chae H, Jo D. Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP Progress in Nuclear Energy. 71: 1-8. DOI: 10.1016/J.Pnucene.2013.10.015  0.365
2014 Jo D, Lee KH, Kim HC, Chae H. Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production Annals of Nuclear Energy. 71: 467-474. DOI: 10.1016/J.Anucene.2014.04.017  0.337
2013 AL-Yahia OS, Albati MA, Park J, Chae H, Jo D. Transient thermal hydraulic analysis of the IAEA 10 MW MTR reactor during Loss of Flow Accident to investigate the flow inversion Annals of Nuclear Energy. 62: 144-152. DOI: 10.1016/J.Anucene.2013.06.010  0.368
2012 Jo D, Park S, Park J, Chae H, Lee B. Cooling capacity of plate type research reactors during the natural convective cooling mode Progress in Nuclear Energy. 56: 37-42. DOI: 10.1016/J.Pnucene.2011.12.018  0.342
2011 Jo D, Revankar ST. Investigation of bubble breakup and coalescence in a packed-bed reactor - Part 1: A comparative study of bubble breakup and coalescence models International Journal of Multiphase Flow. 37: 995-1002. DOI: 10.1016/J.Ijmultiphaseflow.2011.06.016  0.6
2011 Jo D, Revankar ST. Investigation of bubble breakup and coalescence in a packed-bed reactor - Part 2: Development of a new bubble breakup and coalescence model International Journal of Multiphase Flow. 37: 1003-1012. DOI: 10.1016/J.Ijmultiphaseflow.2011.06.015  0.602
2010 Kim SK, Ko WI, Kim HD, Revankar ST, Zhou W, Jo D. Cost-benefit analysis of BeO-UO2 nuclear fuel Progress in Nuclear Energy. 52: 813-821. DOI: 10.1016/J.Pnucene.2010.07.008  0.614
2010 Jo D, Revankar ST. Effect of coalescence and breakup on bubble size distributions in a two-dimensional packed bed Chemical Engineering Science. 65: 4231-4238. DOI: 10.1016/J.Ces.2010.04.019  0.593
2009 Jo D, Revankar ST. Bubble mechanisms and characteristics at pore scale in a packed-bed reactor Chemical Engineering Science. 64: 3179-3187. DOI: 10.1016/J.Ces.2009.04.006  0.591
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