| 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 | 64 | 2014 |
| 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 | 59 | 2018 |
| 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 | 48 | 2017 |
| 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 | 21 | 2018 |
| 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 | 21 | 2013 |
| 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 | 17 | 2014 |
| 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 | 16 | 2018 |
| Bubble dynamic parameters during subcooled flow boiling under uniform and non-uniform transverse heat distribution OS Al-Yahia, HJ Yoon, D Jo International Journal of Heat and Mass Transfer 143, 118508, 2019 | 12 | 2019 |
| 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 | 11 | 2017 |
| Transient analyses of the Jordanian 5 MW research reactor under LOEP accident OS Al-Yahia, H Lee, D Jo Annals of Nuclear Energy 87, 575-583, 2016 | 10 | 2016 |
| Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS) OS Al-Yahia, I Clifford, WM Bissels, D Suckow, H Ferroukhi Nuclear Engineering and Design 405, 112224, 2023 | 8 | 2023 |
| Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution OS Al-Yahia, HJ Yoon, D Jo Nuclear Engineering and Technology 52 (12), 2771-2788, 2020 | 7 | 2020 |
| Prediction of the minimum point of the pressure drop in a narrow rectangular channel under a transversely non-uniform heat flux T Kim, YJ Song, OS Al-Yahia, D Jo Annals of Nuclear Energy 122, 163-174, 2018 | 7 | 2018 |
| Validation of RELAP5 MOD3. 3 code for Hybrid-SIT against SET and IET experimental data HJ Yoon, W Al Naqbi, OS Al-Yahia, D Jo Nuclear Engineering and Technology 52 (9), 1926-1938, 2020 | 5 | 2020 |
| The feasibility study on development of porous ceramic composites for ion-exchanger OS Al-Yahia, S Lee, HJ Ryu, HJ Yoon Nuclear Engineering and Design 381, 111329, 2021 | 4 | 2021 |
| Performance test of 3D printed ceramic filters for capturing of radioisotopes from a nuclear reactor coolant S Lee, OSI Al-Yahia, T Kim, HJ Yoon, HJ Ryu Korea Nuclear Society (KNS), 2020 | 4 | 2020 |
| Experimental study of uniform and non-uniform transverse heat flux distribution effect on the onset of nucleate boiling OS Al-Yahia, T Kim, D Jo International Conference on Nuclear Engineering 57878, V009T15A015, 2017 | 4 | 2017 |
| AL-Yahia, Mohammad A. Albati, Jonghark Park, Heetaek Chae, Daeseong Jo,“Transient Thermal Hydraulic Analysis of The IAEA 10 MW MTR Reactor During Loss of Flow Accident to … S Omar Annals of Nuclear Energy 62, 144-152, 2013 | 4 | 2013 |
| TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system OS Al-Yahia, I Clifford, K Nikitin, P Liu, H Ferroukhi Nuclear Engineering and Design 406, 112234, 2023 | 3 | 2023 |
| Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility OS Al-Yahia, I Clifford, H Ferroukhi Nuclear Engineering and Technology, 2024 | 1 | 2024 |