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Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
Open the PDF for Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor in another window
Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
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
Open the PDF for Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
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
Open the PDF for Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool in another window
Topics: Computational fluid dynamics, Heat sinks, Sodium fast reactors, Thermal stratification
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93039
https://doi.org/10.1115/ICONE29-93039
View Paper titled, Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor
Open the PDF for Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor in another window
Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
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
Open the PDF for Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors
Proceedings Papers

Investigation of Applicability of Subchannel Analysis Code ASFRE on Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure in Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
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, V003T08A019, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65662
https://doi.org/10.1115/ICONE28-65662
View Paper titled, Investigation of Applicability of Subchannel Analysis Code ASFRE on Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure in Sodium Cooled Fast Reactor
Open the PDF for Investigation of Applicability of Subchannel Analysis Code ASFRE on Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure in Sodium Cooled Fast Reactor in another window
Topics: Design, Ducts, Fuels, Manufacturing, Sodium fast reactors, Thermal hydraulics
Proceedings Papers

Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions

Erina Hamase, Norihiro Doda, Ayako Ono, Masaaki Tanaka, Yasuhiro Miyake, Yasutomo Imai
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63380
https://doi.org/10.1115/ICONE28-63380
View Paper titled, Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions
Open the PDF for Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Heat exchangers, Sodium fast reactors, Fuels, Reactor vessels, Sodium, Coolants, Cooling, Cooling systems
Journal Articles

Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021001.
Paper No: NERS-17-1280
https://doi.org/10.1115/1.4042191
Published Online: March 15, 2019
View Article titled, Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor
Open the PDF for Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor in another window
Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium, Temperature distribution, Temperature, Sodium fast reactors, Wire, Thermal hydraulics
Proceedings Papers

Thermal-Hydraulic Analysis of Fuel Assembly With Inner Duct Structure of an Advanced Loop-Type Sodium-Cooled Fast Reactor Using ASFRE Code

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67870
https://doi.org/10.1115/ICONE25-67870
View Paper titled, Thermal-Hydraulic Analysis of Fuel Assembly With Inner Duct Structure of an Advanced Loop-Type Sodium-Cooled Fast Reactor Using ASFRE Code
Open the PDF for Thermal-Hydraulic Analysis of Fuel Assembly With Inner Duct Structure of an Advanced Loop-Type Sodium-Cooled Fast Reactor Using ASFRE Code in another window
Topics: Ducts, Fuels, Manufacturing, Sodium fast reactors, Pins (Engineering), Flow (Dynamics), Temperature distribution, Design, Thermal hydraulics, Turbulence