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Nobuyuki Kimura
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Proceedings Papers

Numerical Study on Passive Control of Thermal Striping Phenomenon Using Lorentz Force in Fast Reactor

Takashi Takata, Takeshi Fukuda, Akira Yamaguchi, Akihiro Uchibori, Nobuyuki Kimura, Hideki Kamide
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 1125-1131, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30188
https://doi.org/10.1115/ICONE18-30188
View Paper titled, Numerical Study on Passive Control of Thermal Striping Phenomenon Using Lorentz Force in Fast Reactor
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Topics: Fast neutron reactors, Passive control, Fatigue, Flow (Dynamics), Magnetic fields, Sodium, Turbulence, Fluids, Junctions, Temperature
Proceedings Papers

Direct Observation and Control of Liquid Sodium Flow Dynamics Using VUV-LIF-PIV Technique Under EXB Lorentz Force

Takeshi Fukuda, Takashi Takata, Hiroshi Horiike, Nobuyuki Kimura, Hideaki Kamide
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 623-628, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29671
https://doi.org/10.1115/ICONE18-29671
View Paper titled, Direct Observation and Control of Liquid Sodium Flow Dynamics Using VUV-LIF-PIV Technique Under EXB Lorentz Force
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Topics: Flow (Dynamics), Sodium, Dynamics (Mechanics), Electrons, Fast neutron reactors, Human eye, Large eddy simulation, Laser beams, Magnetic fields, Metals
Proceedings Papers

Development of High Cycle Thermal Fatigue Evaluation Method Based on Time Interval of Peak-to-Peak of Fluid Temperature

Nobuyuki Kimura, Jun Kobayashi, Hideki Kamide
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 3, 1007-1015, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25595
https://doi.org/10.1115/PVP2010-25595
View Paper titled, Development of High Cycle Thermal Fatigue Evaluation Method Based on Time Interval of Peak-to-Peak of Fluid Temperature
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Topics: Cycles, Evaluation methods, Fatigue, Fluids, Temperature, Waves, Thermal stresses, Construction, Fast neutron reactors, Fatigue damage
Journal Articles

Experimental Study on Gas Entrainment Due to Nonstationary Vortex in a Sodium Cooled Fast Reactor—Comparison of Onset Conditions Between Sodium and Water

Nobuyuki Kimura, Toshiki Ezure, Hiroyuki Miyakoshi, Hideki Kamide, Takeshi Fukuda
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102908.
https://doi.org/10.1115/1.4000621
Published Online: July 6, 2010
View Article titled, Experimental Study on Gas Entrainment Due to Nonstationary Vortex in a Sodium Cooled Fast Reactor—Comparison of Onset Conditions Between Sodium and Water
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Topics: Sodium, Vortices, Water, Sodium fast reactors
Proceedings Papers

Experimental Study on Gas Entrainment Due to Non-Stationary Vortex in a Sodium Cooled Fast Reactor: Comparison of Onset Conditions Between Sodium and Water

Nobuyuki Kimura, Toshiki Ezure, Hiroyuki Miyakoshi, Hideki Kamide, Takeshi Fukuda
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 441-448, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75561
https://doi.org/10.1115/ICONE17-75561
View Paper titled, Experimental Study on Gas Entrainment Due to Non-Stationary Vortex in a Sodium Cooled Fast Reactor: Comparison of Onset Conditions Between Sodium and Water
Open the PDF for Experimental Study on Gas Entrainment Due to Non-Stationary Vortex in a Sodium Cooled Fast Reactor: Comparison of Onset Conditions Between Sodium and Water in another window
Topics: Sodium, Sodium fast reactors, Vortices, Water, Flow (Dynamics), Construction, Cycles, Design, Fast neutron reactors, Fluids
Proceedings Papers

Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor: Water Experiment Using a 1/3 Scale 60 Degree Sector Model

Jun Kobayashi, Nobuyuki Kimura, Akira Tobita, Hideki Kamide, Osamu Watanabe, Kazuhiro Ohyama
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 469-478, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75575
https://doi.org/10.1115/ICONE17-75575
View Paper titled, Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor: Water Experiment Using a 1/3 Scale 60 Degree Sector Model
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Topics: Fast neutron reactors, Water, Temperature, Cycles, Fatigue, Fluids, Fuels, Sodium fast reactors, Technology development
Proceedings Papers

Thermal Fatigue Evaluation Method Based on Power Spectrum Density Functions Against Fluid Temperature Fluctuation

Naoto Kasahara, Nobuyuki Kimura, Hideki Kamide
Proc. ASME. PVP2005, Volume 3: Design and Analysis, 503-509, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71307
https://doi.org/10.1115/PVP2005-71307
View Paper titled, Thermal Fatigue Evaluation Method Based on Power Spectrum Density Functions Against Fluid Temperature Fluctuation
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Topics: Density, Evaluation methods, Fatigue, Fluids, Temperature, Thermal stresses, Cycles, Fatigue damage, Flow (Dynamics), Fluctuations (Physics)