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Toshio Nakagiri
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Journal Articles

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021113.
Paper No: NERS-19-1047
DOI: https://doi.org/10.1115/1.4045450
Published Online: January 29, 2020
View Article titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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Topics: Fuels, Heating, Manufacturing, Plasmas (Ionized gases), Accidents, Temperature, Permeability, Melting, Blades
Proceedings Papers

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A014, July 22–26, 2018
Paper No: ICONE26-81411
DOI: https://doi.org/10.1115/ICONE26-81411
View Paper titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
Open the PDF for Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident in another window
Topics: Accidents, Fuels, Heating, Manufacturing, Melting, Plasmas (Ionized gases), Blades, Computerized tomography, Electrons, Engineering prototypes
Journal Articles

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Yuta Abe, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020901.
Paper No: NERS-16-1117
DOI: https://doi.org/10.1115/1.4038911
Published Online: March 5, 2018
View Article titled, Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions
Open the PDF for Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions in another window
Topics: Heating, Plasmas (Ionized gases), Boiling water reactors, Accidents
Proceedings Papers

Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology

Yuta Abe, Ikken Sato, Akihiro Ishimi, Toshio Nakagiri, Yuji Nagae
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, V002T07A004, June 26–30, 2016
Paper No: ICONE24-60249
DOI: https://doi.org/10.1115/ICONE24-60249
View Paper titled, Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology
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Topics: Accidents, Boiling water reactors, Design, Heat conduction, Heating, Plasmas (Ionized gases), Blades, Rods, Uncertainty
Proceedings Papers

Evaluation of Hydrogen Transport Behavior in the Power Rising Test of Japanese Prototype Fast Breeder Reactor Monju

Daisuke Doi, Toshio Nakagiri
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 309-314, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54176
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54176
View Paper titled, Evaluation of Hydrogen Transport Behavior in the Power Rising Test of Japanese Prototype Fast Breeder Reactor Monju
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Topics: Breeder reactors, Engineering prototypes, Hydrogen, Boilers, Temperature, Coolants, Heat transfer, Light water reactors, Cladding systems (Building), Coprecipitation
Proceedings Papers

Equilibrium Partition Coefficients of Cesium and Iodine Between Sodium Pool and the Inert Cover Gas

Shinya Miyahara, Masahiro Nishimura, Toshio Nakagiri
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 65-70, May 17–21, 2010
Paper No: ICONE18-29169
DOI: https://doi.org/10.1115/ICONE18-29169
View Paper titled, Equilibrium Partition Coefficients of Cesium and Iodine Between Sodium Pool and the Inert Cover Gas
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Topics: Equilibrium (Physics), Nuclear fission, Sodium