Somboon Rassame, Ph.D.
Affiliations: | 2012 | Nuclear Engineering | Purdue University, West Lafayette, IN, United States |
Area:
General Engineering, Nuclear EngineeringGoogle:
"Somboon Rassame"Parents
Sign in to add mentor| Takashi Hibiki | grad student | 2012 | Purdue | |
| (Experimental study of void behavior in a suppression pool of a boiling water reactor during the blowdown period of a loss of coolant accident.) | ||||
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Publications
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| Dong C, Rassame S, Zhang L, et al. (2020) Drift-flux correlation for upward two-phase flow in inclined pipes Chemical Engineering Science. 213: 115395 |
| Vechgama W, Silva K, Rassame S. (2019) Validation of Modified ART Mod 2 Code through Comparison with Aerosol Deposition of Cesium Compound in Phébus FPT3 Containment Vessel Science and Technology of Nuclear Installations. 2019: 1-16 |
| Baotong S, Rassame S, Nilsuwankosit S, et al. (2019) Drift-Flux Correlation of Oil–Water Flow in Horizontal Channels Journal of Fluids Engineering-Transactions of the Asme. 141: 31301 |
| Hibiki T, Schlegel JP, Ozaki T, et al. (2018) Corrigendum to "Simplified Two-Group Two-Fluid Model for Three-Dimensional Two-Phase Flow Computational Fluid Dynamics for Vertical Upward Flow" [Prog. Nucl. Energy 108 (2018) 503-516] Progress in Nuclear Energy. 109: 180 |
| Hibiki T, Schlegel JP, Ozaki T, et al. (2018) Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow Progress in Nuclear Energy. 108: 503-516 |
| Hibiki T, Ozaki T, Shen X, et al. (2018) Constitutive equations for vertical upward two-phase flow in rod bundle International Journal of Heat and Mass Transfer. 127: 1252-1266 |
| Rassame S, Hibiki T. (2018) Drift-flux correlation for gas-liquid two-phase flow in a horizontal pipe International Journal of Heat and Fluid Flow. 69: 33-42 |
| Rattanadecho N, Rassame S, Silva K, et al. (2017) Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test Science and Technology of Nuclear Installations. 2017: 1-12 |
| Rassame S, Hibiki T, Ishii M. (2017) ESBWR passive safety system performance under loss of coolant accidents Progress in Nuclear Energy. 96: 1-17 |
| Yang J, Lim J, Choi SW, et al. (2015) Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor Progress in Nuclear Energy. 83: 35-42 |