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Hiroyuki Sato
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Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91761
https://doi.org/10.1115/ICONE29-91761
View Paper titled, Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR
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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat
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

Characteristic Confirmation Test by Using HTTR and Investigation of Absorbing Thermal Load Fluctuation

Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Masato Ono, Yusuke Fujiwara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
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, V002T06A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60355
https://doi.org/10.1115/ICONE24-60355
View Paper titled, Characteristic Confirmation Test by Using HTTR and Investigation of Absorbing Thermal Load Fluctuation
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Topics: Stress, Very high temperature reactors, Temperature, Graphite, Heat, Testing performance, Combined heat and power, Fuels, High temperature, Nuclear power stations
Journal Articles

Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR

Yoshitomo Inaba, Kenji Sekita, Takahiro Nemoto, Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041001.
Paper No: NERS-15-1194
https://doi.org/10.1115/1.4034320
Published Online: October 12, 2016
View Article titled, Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR
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Topics: Coolants, Heat, Heating, Pressure, Temperature, Graphite, Helium, Heat transfer, Stress
Journal Articles

HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity

Hiroyuki Sato, Xing L. Yan, Junya Sumita, Atsuhiko Terada, Yukio Tachibana
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031010.
Paper No: NERS-15-1120
https://doi.org/10.1115/1.4032480
Published Online: June 17, 2016
View Article titled, HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity
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Topics: Combined heat and power, Design, Gas turbines, Heat, Helium, Hydrogen, Safety, Temperature, Very high temperature reactors
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 Velocity Distribution Around the Wrapping Wire in an Inner Subchannel of Fuel Pin Bundle

Masahiro Nishimura, Hiroyuki Sato, Hideki Kamide, Hiroyuki Ohshima, Kazuyoshi Nagasawa, Yasutomo Imai
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 299-308, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54404
https://doi.org/10.1115/ICONE20-POWER2012-54404
View Paper titled, Investigation on Velocity Distribution Around the Wrapping Wire in an Inner Subchannel of Fuel Pin Bundle
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Topics: Fuels, Wire
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

Effects of Graphite Surface Roughness on Bypass Flow Computations for an HTGR

Yu-Hsin Tung, Richard W. Johnson, Hiroyuki Sato
Proc. ASME. PVP2011, Volume 5: High-Pressure Technology; Nondestructive Evaluation; Nuclear Engineering, 311-320, July 17–21, 2011
Publisher: American Society of Mechanical Engineers
Paper No: PVP2011-58053
https://doi.org/10.1115/PVP2011-58053
View Paper titled, Effects of Graphite Surface Roughness on Bypass Flow Computations for an HTGR
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Topics: Computation, Flow (Dynamics), Graphite, Surface roughness, Very high temperature reactors, Computational fluid dynamics, Coolants, Shear stress, Turbulence, Helium
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

A Study on the Thermal Deformation and the Mechanical Properties due to Curing Process of the Encapsulation Resin

Hiroyuki Sato, Qiang Yu, Ryusuke Sone
Proc. ASME. InterPACK2011, ASME 2011 Pacific Rim Technical Conference and Exhibition on Packaging and Integration of Electronic and Photonic Systems, MEMS and NEMS: Volume 1, 185-190, July 6–8, 2011
Publisher: American Society of Mechanical Engineers
Paper No: IPACK2011-52101
https://doi.org/10.1115/IPACK2011-52101
View Paper titled, A Study on the Thermal Deformation and the Mechanical Properties due to Curing Process of the Encapsulation Resin
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Topics: Hardening (Curing), Mechanical properties, Resins, Thermal deformation, Aluminum, Warping, Deformation, Elastic moduli, Reliability, Semiconductors (Materials)
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
Proceedings Papers

Experimental Test Plan of Air Ingress for HTGR

Atsuhiko Terada, Xing L. Yan, Ryutaro Hino, Hiroyuki Sato
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 59-63, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29392
https://doi.org/10.1115/ICONE18-29392
View Paper titled, Experimental Test Plan of Air Ingress for HTGR
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Topics: Very high temperature reactors
Proceedings Papers

Extrapolation of Creep Curve and Creep Life Prediction From Secondary Creep by Evaluation of Strain Rate Change

Hiroyuki Sato
Proc. ASME. POWER2010, ASME 2010 Power Conference, 483-484, July 13–15, 2010
Publisher: American Society of Mechanical Engineers
Paper No: POWER2010-27336
https://doi.org/10.1115/POWER2010-27336
View Paper titled, Extrapolation of Creep Curve and Creep Life Prediction From Secondary Creep by Evaluation of Strain Rate Change
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Topics: Creep, Shapes, Heat resistant materials, Stress, Temperature
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