Somboon Rassame

Cited by

	All	Since 2019
Citations	367	273
h-index	12	11
i10-index	17	12

2013201420152016201720182019202020212022202320243 6 18 15 30 20 55 40 50 47 57 21

Public access

View all

1 article

2 articles

available

not available

Based on funding mandates

Co-authors

Takashi HibikiCity University of Hong KongVerified email at cityu.edu.hk
Mamoru IshiiDistinguished Professor of Nuclear Engineering in Purdue UniversityVerified email at purdue.edu
Jun YangHuazhong University of Science and TechnologyVerified email at hust.edu.cn
sungwon choiNuclear research scientistVerified email at eri-world.com
Joshua SchlegelAssociate Professor of Nuclear Engineering, Missouri University of Science and TechnologyVerified email at mst.edu
Yang LiuAssociate Professor, Nuclear Engineering Program, Mechanical Engineering Department, Virginia TechVerified email at vt.edu
Won Sik YangUniversity of MichiganVerified email at umich.edu
Shanbin ShiAssistant Professor, Rensselaer Polytechnic InstituteVerified email at rpi.edu
Juyuan YangPhD student, Georgia Institute of TechnologyVerified email at gatech.edu

Somboon Rassame

Department of Nuclear Engineering, Faculty of Engineering, Chulalongkorn Univiersity

Verified email at chula.ac.th

Thermal-Hydraulics Nuclear Reactor Safety Two-Phase Flow Nuclear Engineering


Title Sort by citations Sort by year Sort by title	Cited by Cited by	Year
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	36	2014
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	32	2018
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	22	2015
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
ESBWR passive safety system performance under loss of coolant accidents S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 96, 1-17, 2017	19	2017
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	19	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	19	2012
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	18	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	15	2013
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	13	2022
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	13	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	12	2020
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	11	2020
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, 2019	11	2019
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	11	2018
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
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	11	2014
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
Drift-flux correlation of oil–water flow in horizontal channels S Baotong, S Rassame, S Nilsuwankosit, T Hibiki Journal of Fluids Engineering 141 (3), 031301, 2019	7	2019
Investigation and Modification of Aerosol Deposition Model of ART Mod 2 using Experimental Data from NSPP-502 and Phébus FPT1 W Vechgama, S Rassame, K Silva The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2016	7	2016

The system can't perform the operation now. Try again later.

Articles 1–20

Citations per year

Duplicate citations

Merged citations

Add co-authorsCo-authors

Follow

Cited by

Co-authors