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Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
View Article titled, ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
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Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation
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

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64525
https://doi.org/10.1115/ICONE28-64525
View Paper titled, ARKADIA – for the Innovation of Advanced Nuclear Reactor Design
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Proceedings Papers

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Toshihide Takai, Tomohiro Furukawa, Shigeki Watanabe, Noriko S. Ishioka
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63277
https://doi.org/10.1115/ICONE28-63277
View Paper titled, Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth
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Topics: Alloys, Corrosion, Corrosion resistance, Iron, Oxygen, Stainless steel, Cancer, Fast neutron reactors, Irradiation (Radiation exposure), Mass production
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

Toshihide Takai, Tomohiro Furukawa, 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, V002T08A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16091
https://doi.org/10.1115/ICONE2020-16091
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel
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
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018 in another window
Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Journal Articles

Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility

Hiroo Kondo, Takuji Kanemura, Tomohiro Furukawa, Yasushi Hirakawa, Eiichi Wakai, Juan Knaster
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041005.
Paper No: NERS-16-1045
https://doi.org/10.1115/1.4036513
Published Online: July 31, 2017
View Article titled, Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility
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Topics: Acoustic intensity, Acoustics, Cavitation, Noise (Sound), Pressure, Sensors, Waves, Flow (Dynamics), Pipes, Irradiation (Radiation exposure)
Proceedings Papers

Experimental Study on Lithium Leakage Behavior

Tomohiro Furukawa, Masahiko Ohtaka, Yasushi Hirakawa
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30021
https://doi.org/10.1115/ICONE22-30021
View Paper titled, Experimental Study on Lithium Leakage Behavior
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Topics: Leakage, Lithium, Fire, Carbon, Fluorescence, Density, Irradiation (Radiation exposure), Lasers, Sensors
Proceedings Papers

Basic Experiment on Lithium Removal Technique

Tomohiro Furukawa, Yasushi Hirakawa
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 9-13, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54209
https://doi.org/10.1115/ICONE20-POWER2012-54209
View Paper titled, Basic Experiment on Lithium Removal Technique
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Topics: Lithium, Water, Ethanol, Temperature, Chemical reactions, Hydrogen, Testing, High temperature, Irradiation (Radiation exposure), Low temperature
Proceedings Papers

Experimental Study on Fire-Extinguishing of Lithium

Tomohiro Furukawa, Shoichi Kato, Yasushi Hirakawa, Hiroo Kondo, Hiroo Nakamura
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 517-522, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29262
https://doi.org/10.1115/ICONE18-29262
View Paper titled, Experimental Study on Fire-Extinguishing of Lithium
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Topics: Fire, Lithium, Combustion, Flames, Sands, Temperature, Chemical reactions, Density, Silicon
Proceedings Papers

Corrosion Behavior of FBR Structural Materials in High Temperature Supercritical CO 2

Tomohiro Furukawa, Yoshiyuki Inagaki, Masanori Aritomi
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 307-312, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75121
https://doi.org/10.1115/ICONE17-75121
View Paper titled, Corrosion Behavior of FBR Structural Materials in High Temperature Supercritical CO 2
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Topics: Corrosion, High temperature, Supercritical carbon dioxide, Steel, Weight (Mass), Carbon dioxide, Oxidation, Temperature, Base metals, Breeder reactors
Proceedings Papers

Corrosion Behavior of Steels in Lead-Bismuth Eutectic: In Stagnant LBE Test at Low Oxygen Partial Pressure

Tomohiro Furukawa, Eiichi Yoshida, Kazumi Aoto
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 235-238, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49061
https://doi.org/10.1115/ICONE12-49061
View Paper titled, Corrosion Behavior of Steels in Lead-Bismuth Eutectic: In Stagnant LBE Test at Low Oxygen Partial Pressure
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Topics: Corrosion, Oxygen, Pressure, Steel, Martensitic steel, Molybdenum, Scanning electron microscopy
Journal Articles

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Tai Asayama, Yasuhiro Abe, Noriko Miyaji, Mamoru Koi, Tomohiro Furukawa, Eiichi Yoshida
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. February 2001, 123(1): 49–57.
https://doi.org/10.1115/1.1338119
Published Online: October 27, 2000
View Article titled, Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors
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Topics: Corrosion, Creep, Design, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Sodium, Steel, Fluence (Radiation measurement), Breeder reactors