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Katsuhiro Ohkawa
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Journal Articles

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

Jun Liao, Katsuhiro Ohkawa, William L. Brown, Richard F. Wright
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041701.
Paper No: NERS-18-1088
https://doi.org/10.1115/1.4042796
Published Online: July 19, 2019
View Article titled, A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors
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Topics: Flow (Dynamics), Pipes, Pressure, Pressurized water reactors, Stratified flow, Water, Steam
Proceedings Papers

Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2

Jeffrey R. Kobelak, Jun Liao, Katsuhiro Ohkawa
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82610
https://doi.org/10.1115/ICONE26-82610
View Paper titled, Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2
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Topics: Simulation, Water, Superheating, Reactor vessels, Accidents, Pressurized water reactors, Test facilities, Transients (Dynamics), Boiling, Coolants
Proceedings Papers

Development of WCOBRA/TRAC-TF2 Computer Code: Coupling of the 3D Module (COBRA-TF) With the 1D Module of TRAC-PF1/MOD2

Cesare Frepoli, Katsuhiro Ohkawa, Mitch Nissley
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 829-841, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-76044
https://doi.org/10.1115/ICONE17-76044
View Paper titled, Development of WCOBRA/TRAC-TF2 Computer Code: Coupling of the 3D Module (COBRA-TF) With the 1D Module of TRAC-PF1/MOD2
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Topics: Computers, Fluids, Pacific Ocean, Pressurized water reactors, Simulation, Two-phase flow, Vessels
Proceedings Papers

Void Fraction Predictions in Rod Bundles at Low-Pressure Low-Flow Conditions Based on Cunningham-Yeh Model

Cesare Frepoli, Katsuhiro Ohkawa
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 727-736, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49437
https://doi.org/10.1115/ICONE12-49437
View Paper titled, Void Fraction Predictions in Rod Bundles at Low-Pressure Low-Flow Conditions Based on Cunningham-Yeh Model
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Topics: Flow (Dynamics), Fuel rods, Porosity, Pressure, Boiling, Accidents, Coolants, Databases, Design, Drag (Fluid dynamics)