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Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.
Paper No: NERS-21-1055
DOI: https://doi.org/10.1115/1.4051443
Published Online: October 19, 2021
View Article titled, Post-Test Analyses of the CMMR-4 Test
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Topics: Blades, Boiling water reactors, Cutting, Fuels, Heating, Melting, Water, Temperature, Accidents, Permeability
Proceedings Papers

Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3

Xin Li, Akifumi Yamaji, Masahiro Furuya, Ikken Sato, Hiroshi Madokoro, Yuji Ohishi
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A027, August 4–6, 2021
Paper No: ICONE28-64540
DOI: https://doi.org/10.1115/ICONE28-64540
View Paper titled, Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3
Click here to open pdf in another window PDF for Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3
Topics: Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Vessels
Proceedings Papers

Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3

Ikken Sato, Akifumi Yamaji, Xin Li, Hiroshi Madokoro
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A016, August 4–6, 2021
Paper No: ICONE28-64246
DOI: https://doi.org/10.1115/ICONE28-64246
View Paper titled, Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3
Click here to open pdf in another window PDF for Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3
Topics: Cooling, Floods, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Vessels, Water
Proceedings Papers

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

Yuta Abe, Yusuke Tsuchikawa, Tetsuya Kai, Yoshihiro Matsumoto, Joseph D. Parker, Takenao Shinohara, Yuji Ohishi, Takashi Kamiyama, Yuji Nagae, Ikken Sato
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A050, August 4–5, 2020
Paper No: ICONE2020-16723
DOI: https://doi.org/10.1115/ICONE2020-16723
View Paper titled, Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)
Click here to open pdf in another window PDF for Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)
Topics: Boron, Fukushima nuclear disaster, Japan, 2011, Imaging, Melting, Neutrons, Nuclear decommissioning, Nuclear power stations, Visualization
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

Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method

Xin Li, Ikken Sato, Akifumi Yamaji, Guangtao Duan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A023, July 22–26, 2018
Paper No: ICONE26-82037
DOI: https://doi.org/10.1115/ICONE26-82037
View Paper titled, Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method
Click here to open pdf in another window PDF for Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method
Topics: Concretes, Ablation (Vaporization technology), Particulate matter, Modeling, Containment, Metals, Accident management, Accidents, Cavities, Computer simulation
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
Click here to open pdf in another window PDF for Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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
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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
Click here to open pdf in another window PDF for 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
Topics: Accidents, Boiling water reactors, Design, Heat conduction, Heating, Plasmas (Ionized gases), Blades, Rods, Uncertainty
Proceedings Papers

Development of PIRT (Phenomena Identification and Ranking Table) for SAS-SFR (SAS4A) Validation

Ken-ichi Kawada, Ikken Sato, Yoshiharu Tobita, Werner Pfrang, Laurence Buffe, Emmanuelle Dufour
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A023, July 7–11, 2014
Paper No: ICONE22-30679
DOI: https://doi.org/10.1115/ICONE22-30679
View Paper titled, Development of PIRT (Phenomena Identification and Ranking Table) for SAS-SFR (SAS4A) Validation
Click here to open pdf in another window PDF for Development of PIRT (Phenomena Identification and Ranking Table) for SAS-SFR (SAS4A) Validation
Topics: Sodium fast reactors, Accidents, Coolants, Boiling, Fuels, Transients (Dynamics), Failure, Flow (Dynamics), Heat, Temperature