| Drift-flux correlation for gas-liquid two-phase flow in a horizontal pipe S Rassame, T Hibiki International Journal of Heat and Fluid Flow 69, 33-42, 2018 | 38 | 2018 |
| Flow characteristics and void fraction prediction in large diameter pipes X Shen, JP Schlegel, S Chen, S Rassame, MJ Griffiths, T Hibiki, M Ishii Frontiers and Progress in Multiphase Flow I, 55-103, 2014 | 35 | 2014 |
| ESBWR passive safety system performance under loss of coolant accidents S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 96, 1-17, 2017 | 23 | 2017 |
| Novel modular natural circulation BWR design and safety evaluation M Ishii, S Shi, WS Yang, Z Wu, S Rassame, Y Liu Annals of Nuclear Energy 85, 220-227, 2015 | 23 | 2015 |
| Assessment of passive safety system performance under main steam line break accident J Lim, SW Choi, J Yang, DY Lee, S Rassame, T Hibiki, M Ishii Annals of Nuclear Energy 64, 287-294, 2014 | 21 | 2014 |
| Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear engineering and design 247, 128-135, 2012 | 20 | 2012 |
| Channel size effect on drift-flux parameters for adiabatic and boiling two-phase flows T Hibiki, P Ju, S Rassame, S Miwa, X Shen, T Ozaki International Journal of Heat and Mass Transfer 185, 122410, 2022 | 19 | 2022 |
| Drift-flux correlation for upward two-phase flow in inclined pipes C Dong, S Rassame, L Zhang, T Hibiki Chemical Engineering Science 213, 115395, 2020 | 19 | 2020 |
| Constitutive equations for vertical upward two-phase flow in rod bundle T Hibiki, T Ozaki, X Shen, S Miwa, I Kinoshita, T Hazuku, S Rassame International Journal of Heat and Mass Transfer 127, 1252-1266, 2018 | 19 | 2018 |
| Assessment of passive safety system performance under gravity driven cooling system drain line break accident J Lim, J Yang, SW Choi, DY Lee, S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 74, 136-142, 2014 | 19 | 2014 |
| Counterpart experimental study of ISP-42 PANDA tests on PUMA facility J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear Engineering and Design 258, 249-257, 2013 | 16 | 2013 |
| Void penetration length from air injection through a downward large diameter submerged pipe in water pool S Rassame, T Hibiki, M Ishii Annals of Nuclear Energy 94, 832-840, 2016 | 15 | 2016 |
| Modeling and simulation of onset of condensation-induced water hammer T Hibiki, S Rassame, W Liu, L Wang, Q Zhao, D Chong, J Yan Progress in Nuclear Energy 130, 103555, 2020 | 14 | 2020 |
| Inter-comparison of transboundary atmospheric dispersion calculations: A summary of outputs from the ASEAN NPSR benchmark exercise K Silva, P Krisanungkura, N Khunsrimek, W Vechgama, TJ Hao, ... Progress in Nuclear Energy 135, 103718, 2021 | 12 | 2021 |
| Validation of Modified ART Mod 2 code through comparison with aerosol deposition of cesium compound in Phébus FPT3 containment vessel W Vechgama, K Silva, S Rassame Science and Technology of Nuclear Installations 2019 (1), 4081943, 2019 | 12 | 2019 |
| Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture S Rassame, M Griffiths, J Yang, DY Lee, P Ju, SW Choi, T Hibiki, M Ishii Annals of Nuclear Energy 73, 53-67, 2014 | 12 | 2014 |
| Assessment of RELAP/SCDAPSIM MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test: Focusing on Reactor Core Temperature and Hydrogen Production N Rattanadecho, S Rassame, K Silva, C Allison, J Hohorst The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2016 | 11 | 2016 |
| Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow T Hibiki, JP Schlegel, T Ozaki, S Miwa, S Rassame Progress in Nuclear Energy, 2018 | 10 | 2018 |
| Assessment of RELAP5/SCDAPSIM MOD3.4 Prediction Capability Using Power Burst Facility Severe Fuel Damage Test 1-4 N Barisri, N Rattanadecho, S Rassame, K Silva, C Allison, J Hohorst The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2017 | 8 | 2017 |
| Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor J Yang, J Lim, SW Choi, DY Lee, S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 83, 35-42, 2015 | 8 | 2015 |
Takashi HibikiCity University of Hong Kongยืนยันอีเมลแล้วที่ cityu.edu.hk
