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Yoshihiko Ishii
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Proceedings Papers

Development of Inherently Safe Technologies for Large Scale BWRs: (5) Operation Support System for Plant Accidents

Masaki Kanada, Ryota Kamoshida, Yoshihiko Ishii, Tadaaki Ishikawa, Setsuo Arita, Kenichi Katono
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A049, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31104
https://doi.org/10.1115/ICONE22-31104
View Paper titled, Development of Inherently Safe Technologies for Large Scale BWRs: (5) Operation Support System for Plant Accidents
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Topics: Accidents, Boiling water reactors, Sensors, Signals, Simulation, Errors, Natural disasters, Nuclear reactors, Plant design, Simulation results
Proceedings Papers

Analysis of Isolation Condenser Behavior by TRACG Code

Yoshihiko Ishii, Naoyuki Nakadozono, Hitoshi Ochi
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16671
https://doi.org/10.1115/ICONE21-16671
View Paper titled, Analysis of Isolation Condenser Behavior by TRACG Code
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Topics: Condensers (steam plant), Accidents, Countermeasures, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressure, Reactor vessels, Transient heat transfer
Proceedings Papers

Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code

Yoshihiko Ishii, Kazuaki Kitou, Tomohiko Ikegawa, Shin Hasegawa, Hitoshi Ochi
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 55-62, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29285
https://doi.org/10.1115/ICONE18-29285
View Paper titled, Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code
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Topics: Heat, Neutrons, Water temperature, Algorithms, Boiling water reactors, Control algorithms, Design, Neutron sources, Power regulators, Sensors
Proceedings Papers

Analysis of ABWR Critical Control Operation by TRACG Code

Yoshihiko Ishii, Kazuaki Kitou, Tomohiko Ikegawa, Shin Hasegawa, Hitoshi Ochi
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 285-291, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75143
https://doi.org/10.1115/ICONE17-75143
View Paper titled, Analysis of ABWR Critical Control Operation by TRACG Code
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Topics: Algorithms, Design, Diffusion (Physics), Neutrons, Power regulators, Transient analysis, Two-phase flow
Journal Articles

The Plant Feature and Performance of Double MS (Modular Simplified and Medium Small Reactor)

Tomohiko Ikegawa, Yukiko Kawabata, Yoshihiko Ishii, Masayoshi Matsuura, Shizuka Hirako, Takashi Hoshi
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Design Innovations
J. Eng. Gas Turbines Power. January 2010, 132(1): 015001.
https://doi.org/10.1115/1.3125305
Published Online: October 1, 2009
View Article titled, The Plant Feature and Performance of Double MS (Modular Simplified and Medium Small Reactor)
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Topics: Construction, Design, Emergency core cooling systems, Flow (Dynamics), Pressure, Safety, Steam, Transients (Dynamics), Fuels, Water
Proceedings Papers

Transient Performance of Medium Small LWR “DMS-400” Evaluated Using TRACG Code

Tomohiko Ikegawa, Yoshihiko Ishii, Masayoshi Matsuura, Takashi Hoshi
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 389-394, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48610
https://doi.org/10.1115/ICONE16-48610
View Paper titled, Transient Performance of Medium Small LWR “DMS-400” Evaluated Using TRACG Code
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Topics: Light water reactors, Transients (Dynamics), Heat flux, Steam, Flow (Dynamics), Porosity, Pressure, Separation (Technology), Thermal energy, Boiling water reactors