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Proceedings Papers

Three Pressure Peaks Analysis for the TEPCO Fukushima Daiichi Unit 2 by the SAMPSON Code

Chiaki Kino, Hiroaki Suzuki, Itsuo Yoshioka, Hidetoshi Okada, Masanori Naitoh
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A027, July 2–6, 2017
Paper No: ICONE25-68020
DOI: https://doi.org/10.1115/ICONE25-68020
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Topics: Fukushima nuclear disaster, Japan, 2011, Pressure, Accidents, Nuclear decommissioning, Relief valves, Safety, Simulation results
Proceedings Papers

Eulerian Two-Phase Flow Modeling of Steam Direct Contact Condensation for the Fukushima Accident Investigation

Marco Pellegrini, Giulia Agostinelli, Hidetoshi Okada, Masanori Naitoh
Proc. ASME. FEDSM2014, Volume 1C, Symposia: Fundamental Issues and Perspectives in Fluid Mechanics; Industrial and Environmental Applications of Fluid Mechanics; Issues and Perspectives in Automotive Flows; Gas-Solid Flows: Dedicated to the Memory of Professor Clayton T. Crowe; Numerical Methods for Multiphase Flow; Transport Phenomena in Energy Conversion From Clean and Sustainable Resources; Transport Phenomena in Materials Processing and Manufacturing Processes, V01CT23A011, August 3–7, 2014
Paper No: FEDSM2014-21766
DOI: https://doi.org/10.1115/FEDSM2014-21766
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Topics: Condensation, Fukushima nuclear disaster, Japan, 2011, Modeling, Steam, Two-phase flow, Fluids, Computational fluid dynamics, Bubbles, Accidents, Boiling
Proceedings Papers

Eulerian Two-Phase Flow Modeling of Steam Direct Contact Condensation for the Fukushima Accident Investigation

Marco Pellegrini, Giulia Agostinelli, Hidetoshi Okada, Masanori Naitoh
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A040, July 7–11, 2014
Paper No: ICONE22-30937
DOI: https://doi.org/10.1115/ICONE22-30937
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Topics: Condensation, Fukushima nuclear disaster, Japan, 2011, Modeling, Steam, Two-phase flow, Fluids, Computational fluid dynamics, Bubbles, Accidents, Boiling
Proceedings Papers

Analysis of Accident Progression of Fukushima Daiichi NPP by the SAMPSON Code

Masanori Naitoh, Marco Pellegrini, Hiroaki Suzuki, Hideo Mizouchi, Hidetoshi Okada
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A021, July 7–11, 2014
Paper No: ICONE22-30607
DOI: https://doi.org/10.1115/ICONE22-30607
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Fuels, Heat, Buckling, Condensers (steam plant), Engines, Failure, Fire
Proceedings Papers

Analysis of Melt Progression and Debris Cooling at the Fukushima Daiichi Unit 3 by the SAMPSON code

Marco Pellegrini, Hideo Mizouchi, Hiroaki Suzuki, Masanori Naitoh
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A037, July 7–11, 2014
Paper No: ICONE22-30935
DOI: https://doi.org/10.1115/ICONE22-30935
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Topics: Cooling, Fukushima nuclear disaster, Japan, 2011, Boiling water reactors, Fuels, Melting, Accidents, Approximation, Chemical reactions, Geometry, Heat
Proceedings Papers

Accident Analysis of Fukushima Daiichi Nuclear Power Plant Unit 2 by the SAMPSON Severe Accident Code

Atsuo Takahashi, Marco Pellegrini, Hideo Mizouchi, Hiroaki Suzuki, Masanori Naitoh
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A011, July 7–11, 2014
Paper No: ICONE22-30670
DOI: https://doi.org/10.1115/ICONE22-30670
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Water, Turbines, Pressure, Pumps, Steam, Boundary-value problems, Cooling systems
Proceedings Papers

Analysis of Accident Progression of Fukushima Daiichi NPPs With SAMPSON Code

Masanori Naitoh, Marco Pellegrini, Hideo Mizouchi, Hiroaki Suzuki, Hidetoshi Okada
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A023, July 29–August 2, 2013
Paper No: ICONE21-16805
DOI: https://doi.org/10.1115/ICONE21-16805
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Damage, Pressure, Stress, Coolants, Cooling systems, Earthquakes, High pressure (Physics)
Proceedings Papers

Function of Isolation Condenser of Fukushima Unit-1 Nuclear Power Plant

Masanori Naitoh, Hiroaki Suzuki, Hidetoshi Okada
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 819-824, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55239
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55239
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Topics: Accidents, Condensers (steam plant), Fukushima nuclear disaster, Japan, 2011, Nuclear power stations
Proceedings Papers

Validation of Code System DRAWTHREE-FAC for Evaluation of Wall Thinning due to Flow Accelerated Corrosion by PWR Feed Water Piping Analysis

Masanori Naitoh, Shunsuke Uchida, Hidetoshi Okada, Seiichi Koshizuka
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 1385-1389, July 17–21, 2011
Paper No: PVP2011-57120
DOI: https://doi.org/10.1115/PVP2011-57120
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Topics: Corrosion, Feedwater, Flow (Dynamics), Pipes, Pressurized water reactors, Computational fluid dynamics, Boundary layers, Mass transfer, Wall thickness, Junctions
Proceedings Papers

Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code

Koji Morita, Shuai Zhang, Tatsumi Arima, Seiichi Koshizuka, Yoshiharu Tobita, Hidemasa Yamano, Takahiro Ito, Noriyuki Shirakawa, Fusao Inoue, Hiroaki Yugo, Masanori Naitoh, Hidetoshi Okada, Yuichi Yamamoto, Masashi Himi, Etsujo Hirano, Sensuke Shimizu, Masaya Oue
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 855-863, May 17–21, 2010
Paper No: ICONE18-29886
DOI: https://doi.org/10.1115/ICONE18-29886
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Topics: Accidents, Sodium fast reactors, Failure, Fuels, Ducts, Freezing, Particulate matter, Simulation, Steel, Boiling
Proceedings Papers

Evaluation of Wall Thinning of PWR Feed Water Piping With the Coupled Model of Static Electrochemical Analysis and Dynamic Double Oxide Layer Analysis

Masanori Naitoh, Shunsuke Uchida, Hidetoshi Okada, Taku Ohira, Seiichi Koshizuka
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1243-1252, July 18–22, 2010
Paper No: PVP2010-25517
DOI: https://doi.org/10.1115/PVP2010-25517
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Topics: Electrochemical analysis, Feedwater, Pipes, Pressurized water reactors, Mass transfer, Computational fluid dynamics, Flow (Dynamics), Turbulence, Boilers, Boundary layers
Proceedings Papers

Evaluation of Wall Thinning Rate Due to Flow Accelerated Corrosion With the Coupled Models of Electrochemical Analysis and Double Oxide Layer Analysis

Masanori Naitoh, Shunsuke Uchida, Yasushi Uehara, Hidetoshi Okada, Seiichi Koshizuka
Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 887-895, July 26–30, 2009
Paper No: PVP2009-77583
DOI: https://doi.org/10.1115/PVP2009-77583
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Topics: Corrosion, Electrochemical analysis, Flow (Dynamics), Countermeasures, Current density, Electrochemistry, Electrolytic corrosion, Feedwater, Mass transfer, Optimization
Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(5) Structural Mechanics Models of COMPASS Code and Verification Analyses

Noriyuki Shirakawa, Yasushi Uehara, Masanori Naitoh, Hidetoshi Okada, Yuichi Yamamoto, Seiichi Koshizuka
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, 425-434, July 12–16, 2009
Paper No: ICONE17-75532
DOI: https://doi.org/10.1115/ICONE17-75532
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Topics: Safety, Sodium fast reactors, Structural analysis, Structural mechanics, Design, Fluid dynamics, Fracture (Materials), Fracture (Process), Particulate matter, Phase transitions
Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(6) SCARABEE BE+3 Analysis With SIMMER-III and COMPASS Codes Featuring Duct-Wall Failure

Yasushi Uehara, Noriyuki Shirakawa, Masanori Naitoh, Hidetoshi Okada, Hidemasa Yamano, Yoshiharu Tobita, Yuichi Yamamoto, Seiichi Koshizuka
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, 435-444, July 12–16, 2009
Paper No: ICONE17-75533
DOI: https://doi.org/10.1115/ICONE17-75533
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Topics: Ducts, Failure, Safety, Sodium fast reactors, Fuels, Model development, Accidents, Freezing, Mesoscopic systems, Metals
Proceedings Papers

Mechanistic Prediction of Void Fraction Distribution in BWR Fuel Assembly Using the Subchannel Code CAPE

Kenji Yoshida, Ryo Yoshida, Isao Kataoka, Masanori Naitoh
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 77-83, July 12–16, 2009
Paper No: ICONE17-75091
DOI: https://doi.org/10.1115/ICONE17-75091
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Topics: Boiling water reactors, Fuels, Manufacturing, Porosity, Production engineering computing, Pressurized water reactors, Subcooling, Boiling, Design, Flow (Dynamics)
Proceedings Papers

R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 1 — Introduction of the Project and Development of Structural Mechanics Module

Seiichi Koshizuka, Jie Liu, Noriyuki Shirakawa, Yasushi Uehara, Masanori Naitoh, Yuichi Yamamoto
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 383-390, May 11–15, 2008
Paper No: ICONE16-48499
DOI: https://doi.org/10.1115/ICONE16-48499
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Topics: Fast neutron reactors, Safety, Scientific computing, Structural analysis, Structural mechanics, Sodium fast reactors, Accidents, Computers, Conceptual design, Education
Proceedings Papers

Mechanistic Prediction of Dryout Heat Flux in Annular Two-Phase Flow

Tomio Okawa, Saeyun Kim, Isao Kataoka, Masanori Naitoh
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 429-435, April 14–18, 2002
Paper No: ICONE10-22282
DOI: https://doi.org/10.1115/ICONE10-22282
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Topics: Heat flux, Two-phase flow, Flow (Dynamics), Critical heat flux, Computer simulation, Density, Drops, Errors, Film flow, Liquid films
Proceedings Papers

Subchannel Analysis with Mechanistic Methods for Thermo-Hydro Dynamics in BWR Fuel Bundles

Kentaro Imura, Kenji Yoshida, Isao Kataoka, Masanori Naitoh
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 115-119, July 17–20, 2006
Paper No: ICONE14-89282
DOI: https://doi.org/10.1115/ICONE14-89282
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Topics: Boiling water reactors, Dynamics (Mechanics), Fuels, Production engineering computing, Errors, Pressurized water reactors, Boiling, Computation, Design, Flow (Dynamics)