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Hirofumi Ohashi
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Proceedings Papers

Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor

Hiroyuki Sato, Takeshi Aoki, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16050
https://doi.org/10.1115/ICONE2020-16050
View Paper titled, Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor
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Topics: Design, Fuels, Safety, Very high temperature reactors
Proceedings Papers

Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)

Takeshi Aoki, Kazuyoshi Isaka, Hiroyuki Sato, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16196
https://doi.org/10.1115/ICONE2020-16196
View Paper titled, Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)
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Topics: Flow (Dynamics), Very high temperature reactors
Proceedings Papers

Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor

Takeshi Aoki, Hiroyuki Sato, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16199
https://doi.org/10.1115/ICONE2020-16199
View Paper titled, Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor
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Topics: Unsteady flow, Very high temperature reactors
Journal Articles

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

Yuki Honda, Hiroyuki Sato, Shigeaki Nakagawa, Hirofumi Ohashi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031013.
Paper No: NERS-17-1253
https://doi.org/10.1115/1.4039066
Published Online: May 16, 2018
View Article titled, Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
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Topics: Accidents, Fuels, Temperature, Uncertainty, Uncertainty analysis, Very high temperature reactors, Heat, Failure
Proceedings Papers

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions: Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

Yuki Honda, Hiroyuki Sato, Shigeaki Nakagawa, Hirofumi Ohashi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67587
https://doi.org/10.1115/ICONE25-67587
View Paper titled, Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions: Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
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Topics: Accidents, Uncertainty analysis, Very high temperature reactors, Uncertainty, Risk, Cycles, Dynamics (Mechanics), Failure, Fuels, Probabilistic risk assessment
Proceedings Papers

Design Approach for Mitigation of Air Ingress in High Temperature Gas-Cooled Reactor

Hiroyuki Sato, Hirofumi Ohashi, Shigeaki Nakagawa
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60232
https://doi.org/10.1115/ICONE24-60232
View Paper titled, Design Approach for Mitigation of Air Ingress in High Temperature Gas-Cooled Reactor
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Topics: Design, Very high temperature reactors, Oxidation, Accidents, Fuels, Rupture, Buoyancy, Cooling, Damage, Flow (Dynamics)
Proceedings Papers

Status and Future Development for Nuclear Cogeneration System GTHTR300C

Xing L. Yan, Hiroyuki Sato, Hirofumi Ohashi, Yukio Tachibana, Kazuhiko Kunitomi
Proc. ASME. POWER2013, Volume 2: Reliability, Availability and Maintainability (RAM); Plant Systems, Structures, Components and Materials Issues; Simple and Combined Cycles; Advanced Energy Systems and Renewables (Wind, Solar and Geothermal); Energy Water Nexus; Thermal Hydraulics and CFD; Nuclear Plant Design, Licensing and Construction; Performance Testing and Performance Test Codes, V002T12A008, July 29–August 1, 2013
Publisher: American Society of Mechanical Engineers
Paper No: POWER2013-98173
https://doi.org/10.1115/POWER2013-98173
View Paper titled, Status and Future Development for Nuclear Cogeneration System GTHTR300C
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Topics: Combined heat and power, Fuels, Heat, High temperature, Design, Energy generation, Hydrogen production, Very high temperature reactors, Construction, Gas turbines
Proceedings Papers

Investigation on Iodine Release Behavior During the Operation of High Temperature Engineering Test Reactor (HTTR)

Shohei Ueta, Hiroyuki Inoi, Yoshitaka Mizutani, Hirofumi Ohashi, Jin Iwatsuki, Nariaki Sakaba, Kazuhiro Sawa
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A038, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16128
https://doi.org/10.1115/ICONE21-16128
View Paper titled, Investigation on Iodine Release Behavior During the Operation of High Temperature Engineering Test Reactor (HTTR)
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Topics: High temperature, Coolants, Isotopes, Testing, Circuits, Cooling, Fuels, Nuclear power, Nuclides, Radiation (Physics)
Proceedings Papers

Control Strategies for VHTR Gas-Turbine System With Dry Cooling

Hiroyuki Sato, Xing L. Yan, Hirofumi Ohashi, Yukio Tachibana, Kazuhiko Kunitomi
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 583-590, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54351
https://doi.org/10.1115/ICONE20-POWER2012-54351
View Paper titled, Control Strategies for VHTR Gas-Turbine System With Dry Cooling
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Topics: Cooling, Gas turbines, Very high temperature reactors, Temperature, Energy generation, Compressors, Coolants, Cycles, Design, Engineering simulation
Proceedings Papers

Safety Characteristics of GTHTR and Safety Demonstration Test Program Using HTTR

Kazuhiko Kunitomi, Xing Yan, Hirofumi Ohashi
Proc. ASME. SMR2011, ASME 2011 Small Modular Reactors Symposium, 375-380, September 28–30, 2011
Publisher: American Society of Mechanical Engineers
Paper No: SMR2011-6611
https://doi.org/10.1115/SMR2011-6611
View Paper titled, Safety Characteristics of GTHTR and Safety Demonstration Test Program Using HTTR
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Topics: Safety, Design, Very high temperature reactors, Accidents, Fuels, High temperature, Pipes, Rupture, Construction, Earthquakes
Proceedings Papers

Conceptual Design of Small-Sized HTGR System for Steam Supply and Electricity Generation (HTR50S)

Hirofumi Ohashi, Hiroyuki Sato, Yujiro Tazawa, Xing L. Yan, Yukio Tachibana, Kazuhiko Kunitomi
Proc. ASME. SMR2011, ASME 2011 Small Modular Reactors Symposium, 51-60, September 28–30, 2011
Publisher: American Society of Mechanical Engineers
Paper No: SMR2011-6558
https://doi.org/10.1115/SMR2011-6558
View Paper titled, Conceptual Design of Small-Sized HTGR System for Steam Supply and Electricity Generation (HTR50S)
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Topics: Conceptual design, Electric power generation, Steam, Very high temperature reactors, Design, Developing nations, Central heating, Combined heat and power, Gas cooled reactors, Heat
Proceedings Papers

Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System

Hiroyuki Sato, Hirofumi Ohashi, Yujiro Tazawa, Nariaki Sakaba, Yukio Tachibana
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 1-10, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29108
https://doi.org/10.1115/ICONE18-29108
View Paper titled, Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System
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Topics: Hydrogen production, Safety, Evaluation methods, Pressure, Temperature, Acceptance criteria, Accidents, Cooling systems, Design, Fuels
Journal Articles

Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System

Hiroyuki Sato, Hirofumi Ohashi, Yujiro Tazawa, Nariaki Sakaba, Yukio Tachibana
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. February 2011, 133(2): 022902.
https://doi.org/10.1115/1.4002351
Published Online: October 29, 2010
View Article titled, Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System
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Topics: Cooling systems, Fuels, Heat transfer, Helium, Hydrogen production, Pressure, Safety, Temperature, Transients (Dynamics), Heat
Proceedings Papers

Demonstration of Nuclear Hydrogen Production Utilizing the Japan’s HTTR: Control Scheme Evaluation of the HTTR-IS Nuclear Hydrogen Production System

Hiroyuki Sato, Nariaki Sakaba, Naoki Sano, Hirofumi Ohashi, Yukio Tachibana, Kazuhiko Kunitomi
Proc. ASME. HTR2008, Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2, 481-490, September 28–October 1, 2008
Publisher: American Society of Mechanical Engineers
Paper No: HTR2008-58044
https://doi.org/10.1115/HTR2008-58044
View Paper titled, Demonstration of Nuclear Hydrogen Production Utilizing the Japan’s HTTR: Control Scheme Evaluation of the HTTR-IS Nuclear Hydrogen Production System
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Topics: Hydrogen production, Cooling systems, Fault diagnosis, Flow (Dynamics), Heat, Helium, Hydrogen, Nuclear reactors, Simulation results, Thermal shock
Proceedings Papers

Experimental and Analytical Study on Chemical Reaction Loss Accident With a Mock-Up Model of HTTR Hydrogen Production System

Hirofumi Ohashi, Tetsuo Nishihara, Tetsuaki Takeda, Yukimasa Maeda, Hiroyuki Sato, Yoshitomo Inaba, Koji Hayashi, Shoji Takada, Yoshiyuki Inagaki
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 507-514, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49419
https://doi.org/10.1115/ICONE12-49419
View Paper titled, Experimental and Analytical Study on Chemical Reaction Loss Accident With a Mock-Up Model of HTTR Hydrogen Production System
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Topics: Accidents, Boilers, Chemical reactions, Hydrogen production, Numerical analysis