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Koji Morita
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Proceedings Papers

Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Koji Morita, Mariano Tarantino, Alessio Pesetti, Vittorio Cossu, Andrei Rineiski
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136243
https://doi.org/10.1115/ICONE31-136243
View Paper titled, Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal
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Topics: Equations of state, Fast neutron reactors, Thermodynamic properties, Heat capacity, Accidents, Design, Liquid metals, Pressure, Sodium fast reactors, Boilers
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041102.
Paper No: NERS-22-1136
https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
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Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Article titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Proceedings Papers

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91812
https://doi.org/10.1115/ICONE29-91812
View Paper titled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications
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Topics: Accidents, Fast neutron reactors, Sodium fast reactors
Proceedings Papers

Development of a Passive Reactor Shutdown Device for Prevention of Core Disruptive Accidents in Fast Reactors: Project Overview and Preliminary Results

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Koharu Kawase, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A013, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64099
https://doi.org/10.1115/ICONE28-64099
View Paper titled, Development of a Passive Reactor Shutdown Device for Prevention of Core Disruptive Accidents in Fast Reactors: Project Overview and Preliminary Results
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Topics: Accidents, Fast neutron reactors, Sodium fast reactors
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Koji Morita, Kinya Nakamura
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63301
https://doi.org/10.1115/ICONE28-63301
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019
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Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

A 3D Numerical Simulation on Heat Transfer Behavior in Eagle ID1 In-Pile Test Using Finite Volume Particle Method

Ting Zhang, Koji Morita, Xiaoxing Liu, Wei Liu, Kenji Kamiyama
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61469
https://doi.org/10.1115/ICONE28-61469
View Paper titled, A 3D Numerical Simulation on Heat Transfer Behavior in Eagle ID1 In-Pile Test Using Finite Volume Particle Method
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Topics: Accidents, Computer simulation, Heat transfer, Particulate matter, Simulation, Sodium fast reactors
Proceedings Papers

A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling

Md. Abdur Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64022
https://doi.org/10.1115/ICONE28-64022
View Paper titled, A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling
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Topics: Boiling, Bubbles, Critical heat flux, Flow (Dynamics), Subcooling, Vapors
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16175
https://doi.org/10.1115/ICONE2020-16175
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide
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Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16102
https://doi.org/10.1115/ICONE2020-16102
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018
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Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

New Super-Low CTE (0.7 ppm/K) Core Material for Next Generation Thin CSP

Yukio Nakamura, Kenichi Oohashi, Koji Morita, Shuji Nomoto, Takayuki Suzuki, Shin Takanezawa, Shinji Tsuchikawa, Masaaki Takekoshi
Proc. ASME. InterPACK2015, Volume 2: Advanced Electronics and Photonics, Packaging Materials and Processing; Advanced Electronics and Photonics: Packaging, Interconnect and Reliability; Fundamentals of Thermal and Fluid Transport in Nano, Micro, and Mini Scales, V002T01A018, July 6–9, 2015
Publisher: American Society of Mechanical Engineers
Paper No: IPACK2015-48836
https://doi.org/10.1115/IPACK2015-48836
View Paper titled, New Super-Low CTE (0.7 ppm/K) Core Material for Next Generation Thin CSP
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Topics: Density, Diluents, Fillers (Materials), Package on package, Resins, Thermal expansion, Warping
Proceedings Papers

Development of Assessment Method for a Self-Leveling Behavior of Debris Bed and Analyses of Experiments

Hirotaka Tagami, Songbai Cheng, Yoshiharu Tobita, Liancheng Guo, Bin Zhang, Koji Morita
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30290
https://doi.org/10.1115/ICONE22-30290
View Paper titled, Development of Assessment Method for a Self-Leveling Behavior of Debris Bed and Analyses of Experiments
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Topics: Accidents, Analytical methods, Boiling, Bubbles, Collisions (Physics), Coolants, Cooling, Deformation, Density, Flow (Dynamics)
Proceedings Papers

Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita
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, V004T10A024, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30618
https://doi.org/10.1115/ICONE22-30618
View Paper titled, Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment
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Topics: Computational fluid dynamics, Discrete element methods, Fluid dynamics, Particulate matter, Liquid metal cooled reactors, Safety, Accidents, Computational methods, Computer simulation, Computers
Proceedings Papers

Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method

Yuki Aramaki, Takahito Suzuki, Ichiro Miya, Liancheng Guo, Koji Morita
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A053, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16688
https://doi.org/10.1115/ICONE21-16688
View Paper titled, Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method
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Topics: Bubbles, Computer simulation, Particulate matter, Simulation, Fluids, Shapes, Discrete element methods, Drag (Fluid dynamics), Flow (Dynamics), Viscosity
Proceedings Papers

Recent Knowledge From an Experimental Investigation on Self-Leveling Behavior of Debris Bed

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A048, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15595
https://doi.org/10.1115/ICONE21-15595
View Paper titled, Recent Knowledge From an Experimental Investigation on Self-Leveling Behavior of Debris Bed
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Topics: Accidents, Boiling, Collaboration, Computers, Coolants, Density, Fast neutron reactors, Flow (Dynamics), Gas flow, Nuclear power
Proceedings Papers

Experimental Evaluation of Debris Bed Characteristics in Particulate Debris Sedimentation Behaviour

M. Shamsuzzaman, Tatsuro Horie, Fusata Fuke, Takayuki Kai, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A009, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15693
https://doi.org/10.1115/ICONE21-15693
View Paper titled, Experimental Evaluation of Debris Bed Characteristics in Particulate Debris Sedimentation Behaviour
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Topics: Particulate matter, Sedimentation, Nozzles, Shapes, Density, Accidents, Computer simulation, Cooling, Gravity (Force), Reactor vessels
Proceedings Papers

Numerical Simulation of Self-Leveling Behavior in Debris Bed by a Hybrid Method

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A019, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15483
https://doi.org/10.1115/ICONE21-15483
View Paper titled, Numerical Simulation of Self-Leveling Behavior in Debris Bed by a Hybrid Method
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Topics: Computer simulation, Particulate matter, Discrete element methods, Fast neutron reactors, Fluid dynamics, Fluids, Safety, Accidents, Algorithms, Flow (Dynamics)
Proceedings Papers

Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III

Bin Zhang, Tatsuya Matsumoto, Koji Morita, Hidemasa Yamano, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 751-760, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54684
https://doi.org/10.1115/ICONE20-POWER2012-54684
View Paper titled, Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III
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Topics: Computer simulation, Particulate matter, Sodium, Accidents, Boiling, Convection, Experimental analysis, Fast neutron reactors, Fluidization, Heat
Proceedings Papers

Numerical Simulation of Three-Phase Flows With Rich Solid Particles by Coupling Multi-Fluid Model With Discrete Element Method

Liancheng Guo, Koji Morita, Yoshiharu Tobita
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 371-382, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54053
https://doi.org/10.1115/ICONE20-POWER2012-54053
View Paper titled, Numerical Simulation of Three-Phase Flows With Rich Solid Particles by Coupling Multi-Fluid Model With Discrete Element Method
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Topics: Computer simulation, Discrete element methods, Flow (Dynamics), Fluids, Particulate matter, Multiphase flow, Fast neutron reactors, Fluid dynamics, Fuels, Safety
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29886
https://doi.org/10.1115/ICONE18-29886
View Paper titled, Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code
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Topics: Accidents, Sodium fast reactors, Failure, Fuels, Ducts, Freezing, Particulate matter, Simulation, Steel, Boiling