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Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
https://doi.org/10.1115/1.4055328
Published Online: December 14, 2022
View Article titled, Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
Proceedings Papers

Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor

Hidemasa Yamano, Shigenobu Kubo, Taro Kan, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91505
https://doi.org/10.1115/ICONE29-91505
View Paper titled, Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor
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Topics: Accidents, Sodium fast reactors, Design, Coolants, Fuels, Probability, Sodium, Vessels
Proceedings Papers

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Hidemasa Yamano, Satoshi Futagami, Masanori Ando
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93231
https://doi.org/10.1115/ICONE29-93231
View Paper titled, Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions
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Topics: Deformation, High temperature, Reactor vessels, Resilience, Sodium fast reactors, Structural analysis
Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93244
https://doi.org/10.1115/ICONE29-93244
View Paper titled, Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model
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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)
Proceedings Papers

Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool

Kazuo Yoshimura, Norihiro Doda, Tatsuya Fujisaki, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89259
https://doi.org/10.1115/ICONE29-89259
View Paper titled, Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool
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Topics: Computational fluid dynamics, Heat sinks, Sodium fast reactors, Thermal stratification
Proceedings Papers

Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Masaaki Tanaka, Hidemasa Yamano, Kennichi Igawa
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, V003T09A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62354
https://doi.org/10.1115/ICONE28-62354
View Paper titled, Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel

Shin Kikuchi, Toshihide Takai, Hidemasa Yamano, Kan Sakamoto
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, V003T12A003, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62252
https://doi.org/10.1115/ICONE28-62252
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Koji Morita, Kinya Nakamura
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, V003T12A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63301
https://doi.org/10.1115/ICONE28-63301
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019
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Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems

Hidemasa Yamano, Marie-Sophie Chenaud, Seok-Hun Kang, Tyler Sumner, Haileyesus Tsige-Tamirat, Jin Wang, Evgeny Rozhikhin
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66385
https://doi.org/10.1115/ICONE28-66385
View Paper titled, Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems
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Topics: Safety, Sodium fast reactors
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16175
https://doi.org/10.1115/ICONE2020-16175
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis

Shin Kikuchi, Hidemasa Yamano, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16075
https://doi.org/10.1115/ICONE2020-16075
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Steel, Thermal analysis
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16091
https://doi.org/10.1115/ICONE2020-16091
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16102
https://doi.org/10.1115/ICONE2020-16102
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018
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Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Development of Seismic Countermeasures Against Cliff Edges for Enhancement of Comprehensive Safety of Nuclear Power Plants: Cliff Edges Relevant to NPP Building System

Akemi Nishida, Byunghyun Choi, Hidemasa Yamano, Tsuyoshi Takada
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A028, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85066
https://doi.org/10.1115/PVP2018-85066
View Paper titled, Development of Seismic Countermeasures Against Cliff Edges for Enhancement of Comprehensive Safety of Nuclear Power Plants: Cliff Edges Relevant to NPP Building System
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Topics: Countermeasures, Nuclear power stations, Safety, Three-dimensional models, Collisions (Physics), Modeling, Boundary-value problems, Damage, Defense industry, Earthquakes
Proceedings Papers

Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling

Hidemasa Yamano, Kenichi Naruto, Kenichi Kurisaka, Hiroyuki Nishino, Yasushi Okano
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81079
https://doi.org/10.1115/ICONE26-81079
View Paper titled, Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling
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Topics: Sodium fast reactors, Storage tanks, Vessels, Failure, Accidents, Sodium, Fuels, Damage, Dampers, Design
Journal Articles

Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka, Takahiro Yamamoto
Journal: ASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg
Publisher: ASME
Article Type: Research-Article
ASME J. Risk Uncertainty Part B. September 2018, 4(3): 030902.
Paper No: RISK-16-1136
https://doi.org/10.1115/1.4037877
Published Online: December 5, 2017
View Article titled, Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors
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Topics: Failure, Filters, Hazards, Probability, Probabilistic risk assessment, Sodium fast reactors, Damage, Heat, Air filters
Proceedings Papers

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors

Hiroyuki Nishino, Hidemasa Yamano, Kenichi Kurisaka
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A038, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67627
https://doi.org/10.1115/ICONE25-67627
View Paper titled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors
Open the PDF for Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors in another window
Topics: Hazards, Heat, Low temperature, Probabilistic risk assessment, Sodium fast reactors, Failure, Probability, Damage, Filters, Accidents
Proceedings Papers

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66059
https://doi.org/10.1115/ICONE25-66059
View Paper titled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors
Open the PDF for Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors in another window
Topics: Hazards, Heat, Probabilistic risk assessment, Sodium fast reactors, Wind, Failure, Missiles, Cooling systems, Drops, Wind velocity
Proceedings Papers

Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka, Yasushi Okano, Takaaki Sakai, Takahiro Yamamoto, Yoshihiro Ishizuka, Nobuo Geshi, Ryuta Furukawa, Futoshi Nanayama, Takashi Takata
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A002, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60023
https://doi.org/10.1115/ICONE24-60023
View Paper titled, Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology
Open the PDF for Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology in another window
Topics: Hazards, Heat, Risk assessment, Sodium fast reactors, Failure, Filters, Probability, Air filters, Damage, Emergency power
Proceedings Papers

Sensitivity Study on Forest Fire Breakout and Propagation Conditions for Forest Fire Hazard Curve Evaluations

Yasushi Okano, Hidemasa Yamano
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60047
https://doi.org/10.1115/ICONE24-60047
View Paper titled, Sensitivity Study on Forest Fire Breakout and Propagation Conditions for Forest Fire Hazard Curve Evaluations
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Topics: Fire, Hazards, Nuclear power stations, Probability, Statistical distributions, Heat, Probabilistic risk assessment, Sodium fast reactors, Databases, Meteorology