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Shigeaki Nakagawa
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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

Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating

Masato Ono, Atsushi Shimizu, Makoto Kondo, Yosuke Shimazaki, Masanori Shinohara, Daisuke Tochio, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044502.
Paper No: NERS-15-1178
https://doi.org/10.1115/1.4032478
Published Online: October 12, 2016
View Article titled, Investigation of Countermeasure Against Local Temperature Rise in Vessel Cooling System in Loss of Core Cooling Test Without Nuclear Heating
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Topics: Cooling, Heating, Temperature, Water, Cooling systems, Vessels, Flow (Dynamics), Heat
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
Proceedings Papers

Preliminary Study on Thermal-Load Fluctuation Test Using HTTR

Daisuke Tochio, Yosuke Shimazaki, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Nariaki Sakaba, Kazuhiro Sawa
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A034, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16082
https://doi.org/10.1115/ICONE21-16082
View Paper titled, Preliminary Study on Thermal-Load Fluctuation Test Using HTTR
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Topics: Stress, Dynamics (Mechanics), Hydrogen production, Combined heat and power, Design, Hydrogen, Industrial plants, Scram, Steady state, Very high temperature reactors
Proceedings Papers

The Preliminary Analysis of the Loss of Primary Coolant Flow Test in the HTTR

Shigeaki Nakagawa, Kuniyoshi Takamatsu, Minoru Goto, Tetsuaki Takeda, Yasuyuki Nakao
Proc. ASME. HTR2008, Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2, 405-412, September 28–October 1, 2008
Publisher: American Society of Mechanical Engineers
Paper No: HTR2008-58282
https://doi.org/10.1115/HTR2008-58282
View Paper titled, The Preliminary Analysis of the Loss of Primary Coolant Flow Test in the HTTR
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Topics: Coolants, Flow (Dynamics), Safety, Very high temperature reactors, Accidents, Fuels, Generation IV reactors, High temperature, Licensing, Rods
Proceedings Papers

Design and Fabrication of Reactor Pressure Vessel for High Temperature Engineering Test Reactor (HTTR)

Yukio Tachibana, Shigeaki Nakagawa, Tatsuo Iyoku
Proc. ASME. PVP2004, Elevated Temperature Design and Analysis, Nonlinear Analysis, and Plastic Components, 39-44, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2257
https://doi.org/10.1115/PVP2004-2257
View Paper titled, Design and Fabrication of Reactor Pressure Vessel for High Temperature Engineering Test Reactor (HTTR)
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Topics: Design, Embrittlement, High temperature, In-service inspection, Manufacturing, Reactor vessels, Steel