| Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor Y Alatrash, H Kang, H Yoon, K Seo, DY Chi, J Yoon Nuclear Engineering and Design 286, 60-66, 2015 | 24 | 2015 |
| Investigation of subcooled boiling wall closures at high pressure using a two-phase CFD code Y Alatrash, YJ Cho, CH Song, HY Yoon Nuclear Engineering and Technology 54 (6), 2276-2296, 2022 | 4 | 2022 |
| Analyses for primary coolant pump coastdown phenomena for Jordan Research and Training Reactor YM Alatrash, H Kang, H Yoon, S Zhang, J Yoon International Conference on Nuclear Thermal Hydraulics and Safety, 27-28, 2014 | 4 | 2014 |
| Experimental and numerical investigation of local bubble parameters for subcooled flow boiling in a pressurized annulus Y Alatrash, YJ Cho, HY Yoon, CH Song, IC Chu International Journal of Heat and Mass Transfer 194, 123040, 2022 | 3 | 2022 |
| Validation of subcooled flow boiling model in the CUPID code Y Alatrash, YJ Cho, HY Yoon 유체기계 연구개발 발표회 논문집, 9-11, 2021 | 1 | 2021 |
| Development of Program for Generation of Thermodynamic Properties Tables in CUPID Code Y Alatrash, HY Yoon, YJ Chob Proceedings of the Korean Nuclear Society Spring Meeting, 2020 | 1 | 2020 |
| EXPERIMENTAL AND NUMERICAL STUDIES FOR SUBCOOLED FLOW BOILING UNDER HIGH PRESSURE CONDITION USING R-134A HYY Yun-Je Cho, Yazan Alatrash Nureth-19, 2022 | | 2022 |
| APPLICATION OF THE CUPID CODE FOR SIMULATION of SUBCOOLED FLOW BOILING PHONOMENA Y Alatrash, HY Yoon, YJ Cho ICAPP-ABU DHABI 2020, 2021 | | 2021 |
| Development of CUPID-Heat Exchanger Model for the Simulation of the Condensation Phenomena inside the PCCS Y Alatrash, HY Yoon, SW Bae, JR Lee, JH Sohn, DW Jerngc | | 2019 |
Jae Ryong LeeKorea Atomic Energy Research InstituteVerified email at kaeri.re.kr
Jae Ryong LeeKorea Atomic Energy Research InstituteVerified email at kaeri.re.kr