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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, V002T06A023, June 26–30, 2016

Paper No: ICONE24-60571

DOI: https://doi.org/10.1115/ICONE24-60571

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Topics: Earthquakes, Inspection, Instrumentation, Very high temperature reactors, Damage, Earthquake resistant design, High temperature, Industrial research, Maintenance, Nuclear power

Journal Articles

Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors

Yosuke Shimazaki, Hiroaki Sawahata, Taiki Kawamoto, Hisashi Suzuki, Masanori Shinohara, Yuki Honda, Kozo Katsuyama, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. October 2016, 2(4): 041008.

Paper No: NERS-15-1201

DOI: https://doi.org/10.1115/1.4032597

Published Online: October 12, 2016

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Topics: Cables, Neutrons, Sensors, Very high temperature reactors, Maintenance

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

ASME J of Nuclear Rad Sci. October 2016, 2(4): 041001.

Paper No: NERS-15-1194

DOI: https://doi.org/10.1115/1.4034320

Published Online: October 12, 2016

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Topics: Coolants, Heat, Heating, Pressure, Temperature, Graphite, Helium, Heat transfer, Stress

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

ASME J of Nuclear Rad Sci. October 2016, 2(4): 044502.

Paper No: NERS-15-1178

DOI: https://doi.org/10.1115/1.4032478

Published Online: October 12, 2016

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Topics: Cooling, Heating, Temperature, Water, Cooling systems, Vessels, Flow (Dynamics), Heat

Proceedings Papers

Influence of Differences Between Seismic Safety Evaluation Methods for Equipment and Piping of a Nuclear Facility

Akemi Nishida, Kazuhiko Iigaki, Kazuhiro Sawa, Yinsheng Li

Proc. ASME. PVP2015, Volume 8: Seismic Engineering, V008T08A014, July 19–23, 2015

Paper No: PVP2015-45913

DOI: https://doi.org/10.1115/PVP2015-45913

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Topics: Evaluation methods, Pipes, Safety, Waves, Cooling systems, Piping systems

Proceedings Papers

Structural Analysis for Assembly by Integrating Parts

Norihiro Nakajima, Akemi Nishida, Yoshiaki Kawakami, Tatsuo Okada, Osamu Tsuruta, Kazuhiro Sawa, Kazuhiko Iigaki

Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A009, July 7–11, 2014

Paper No: ICONE22-30251

DOI: https://doi.org/10.1115/ICONE22-30251

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Topics: Manufacturing, Structural analysis, Computers, Finite element analysis, High temperature, Nuclear power

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

Paper No: ICONE21-16082

DOI: https://doi.org/10.1115/ICONE21-16082

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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

A Safety Evaluation of HTTR Core Components Against 2011 Tohoku Earthquake

Kazuhiko Iigaki, Masato Ono, Yosuke Shimazaki, Daisuke Tochio, Atsushi Shimizu, Hiroyuki Inoi, Shoji Takada, Kazuhiro Sawa

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A035, July 29–August 2, 2013

Paper No: ICONE21-16091

DOI: https://doi.org/10.1115/ICONE21-16091

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Topics: Earthquakes, Safety, Seismic analysis, Design, Graphite, Inspection, Magnification, Optical quality control, Seismic waves, Stress

Proceedings Papers

Improvement of Temperature Evaluation Model of Biological Shielding Concrete for HTTR Test Simulating LOFC With VCS Inactive

Shoji Takada, Shunki Yanagi, Kazuhiko Iigaki, Masanori Shinohara, Daisuke Tochio, Yosuke Shimazaki, Masato Ono, Kazuhiro Sawa

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A036, July 29–August 2, 2013

Paper No: ICONE21-16095

DOI: https://doi.org/10.1115/ICONE21-16095

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Topics: Concretes, Temperature, Cooling, Heat transfer, Fins, Heat conduction, Natural convection, Thermal radiation, Very high temperature reactors, Water

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

Paper No: ICONE21-16128

DOI: https://doi.org/10.1115/ICONE21-16128

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Topics: High temperature, Coolants, Isotopes, Testing, Circuits, Cooling, Fuels, Nuclear power, Nuclides, Radiation (Physics)

Proceedings Papers

Reactor Kinetics in a Loss-of-Forced-Cooling (LOFC) Test of HTGRs

Kuniyoshi Takamatsu, Kazuhiro Sawa

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 659-668, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54641

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54641

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Topics: Cooling, Nuclear reactor kinetics, Very high temperature reactors, Coolants, High temperature, Control systems, Heat, Safety, Temperature, Accidents

Proceedings Papers

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

Shohei Ueta, Jun Aihara, Masaki Honda, Noboru Furihata, Kazuhiro Sawa

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 11-12, May 17–21, 2010

Paper No: ICONE18-29206

DOI: https://doi.org/10.1115/ICONE18-29206

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Topics: Fuels, Very high temperature reactors, Carbon, Coating processes, Coatings, Particulate matter, Nuclear fission, High temperature, Nuclear power, Polishing equipment

Proceedings Papers

RAPHAEL-FT & Generation IV PYCASSO-I Irradiation

Sander de Groot, Virginie Basini, Pierre Guillermier, Klaas Bakker, Kazuhiro Sawa, Young-Woo Lee, Jean-Michel Escleine, Marc Perez, Shohei Ueta, Bong-Goo Kim

Proc. ASME. HTR2008, Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2, 337-346, September 28–October 1, 2008

Paper No: HTR2008-58127

DOI: https://doi.org/10.1115/HTR2008-58127

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Topics: Irradiation (Radiation exposure), Coatings, Manufacturing, Fuels, Particulate matter, Corrosion, Creep, Design, Dimensions, Electrical conductivity

Proceedings Papers

Analytical Study on Micro-Indentation Method to Integrity Evaluation for Graphite Components in HTGR

Junya Sumtia, Satoshi Hanawa, Taiju Shibata, Tatsuya Tada, Tatsuo Iyoku, Kazuhiro Sawa

Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 523-530, July 17–20, 2006

Paper No: ICONE14-89384

DOI: https://doi.org/10.1115/ICONE14-89384

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Topics: Graphite, Very high temperature reactors, Stress, Mechanical properties, Tensile strength

Journal citation

NARROW

Comprehensive Seismic Evaluation of HTTR Against the 2011 Off the Pacific Coast of Tohoku Earthquake

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

Confirmation of Seismic Integrity of HTTR Against 2011 Great East Japan Earthquake

Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors

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

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

Influence of Differences Between Seismic Safety Evaluation Methods for Equipment and Piping of a Nuclear Facility

Structural Analysis for Assembly by Integrating Parts

Preliminary Study on Thermal-Load Fluctuation Test Using HTTR

A Safety Evaluation of HTTR Core Components Against 2011 Tohoku Earthquake

Improvement of Temperature Evaluation Model of Biological Shielding Concrete for HTTR Test Simulating LOFC With VCS Inactive

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

Reactor Kinetics in a Loss-of-Forced-Cooling (LOFC) Test of HTGRs

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

RAPHAEL-FT & Generation IV PYCASSO-I Irradiation

Analytical Study on Micro-Indentation Method to Integrity Evaluation for Graphite Components in HTGR

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