Nuclear Engineering and Technology (52) 2771-2788 Al-Yahia, Ho Joon Yoon, Daeseong Jo* (2020) Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution. Journal of Mechanical Science and Technology (34) 1913-1923 Hongrae Jo, Yeongmin Kim, Daeseong Jo* (2020) Acoustically monitoring defects on rotating turbine blades.International Journal of Heat and Mass Transfer (153) Article 119620 Tanjung, Daeseong Jo* (2020) Visualization study on pool boiling critical heat flux under rolling motion. Nuclear Engineering and Technology (52) 1926-1938
Al-Yahia, Daeseong Jo (2020) Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data. Ho Joon Yoon*, Waleed Al Naqbi, Omar S.Nuclear Engineering and Technology (52) 520-529 Jeong, Daeseong Jo* (2020) Critical heat flux (CHF) in pool boiling under static and rolling conditions. Annals of Nuclear Energy (139) Article 107267 Hongrae Jo, Yong Jae Song, Daeseong Jo* (2020) Non-intrusive detection of gas-water interface in circular pipes inclined at various angles.International Communications in Heat and Mass Transfer (119) Article 104964 Young Seock An, Daeseong Jo, Byoung Jae Kim* (2020) Multimode film boiling on a horizontal surface in a vertically oscillating system.Nuclear Engineering and Technology (53) 4003-4013 Yong Jae Song*, Dong Seok Lim, Min Beom Heo, Beom Kyu Kim, Doo Yong Lee, Daeseong Jo, (2021) Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants.Progress in Nuclear Energy (136) Article 103731 Geoseong Na, Ji-Hwan Park, Hongrae Jo, Daeseong Jo* (2021) Measuring void fraction in vertical air-water flow using echo intensity and visualization techniques.Thinh Quy Duc Pham, Jichan Jeon, Daeseong Jo, Sanghun Choi* (2021) Two-phase flow simulations using 1D centerline-based C- and U-shaped pipe meshes.Annals of Nuclear Energy (154) Article 108095 Tanjung, Byoung Jae Kim, Daeseong Jo* (2021) Effects on pool boiling critical heat flux (CHF) with different direction and magnitude of additional accelerations due to rolling. Nuclear Engineering and Design (375) Article 111090 Tae Wook Ha, Sung Won Bae, Jonh-Pil Park, Daeseong Jo, Byong-Jo Yun, Jae Jun Jeong* (2021) Development of an empirical correlation for the onset of flow instability in narrow rectangular channels.Annals of Nuclear Energy (151) Article 107967 Tanjung, Daeseong Jo* (2021) Experimental study of critical heat flux mechanism on a vertical heated surface under rolling motion. Annals of Nuclear Energy (150) Article 107863 Ji-Hwan Park, Ilchung Park, Daeseong Jo* (2021) Statistical method for determining the onset of nucleate boiling under forced and natural circulations in a rectangular channel.