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Proceedings Papers

Calculation of Critical Heat Flux Using an Inverse Heat Transfer Method to Support TREAT Experiment Analysis

Robert Armstrong, Charles Folsom, Connie Hill, Colby Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A032, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16632
https://doi.org/10.1115/ICONE2020-16632
View Paper titled, Calculation of Critical Heat Flux Using an Inverse Heat Transfer Method to Support TREAT Experiment Analysis
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Topics: Critical heat flux, Experimental analysis, Heat transfer, Transients (Dynamics)
Proceedings Papers

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Richard Hernandez, Nicholas R. Brown, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A041, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16758
https://doi.org/10.1115/ICONE2020-16758
View Paper titled, RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT
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Topics: Boron, Critical heat flux, Pool boiling, Testing, Coolants, Design, Shapes, Accidents, Heat flux, Heat transfer
Proceedings Papers

QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5

C. Allison, B. T. Le, G. Gerova, I. Spasov, M. Perez-Ferragut, J. Hohorst
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81912
https://doi.org/10.1115/ICONE26-81912
View Paper titled, QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5
Open the PDF for QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5 in another window
Topics: Uncertainty analysis, Modeling, Heat losses, Internships, Uncertainty, Computer software, Contact resistance, Convection, Experimental analysis, Fuel rods
Proceedings Papers

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

Zhen-Yu Hung, Pei-Hsun Huang, Chao-Jen Li
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81074
https://doi.org/10.1115/ICONE26-81074
View Paper titled, Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation
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Topics: Safety, Transportation systems, Computer software, Containment, Corrective actions, Design, Emergency core cooling systems, Experimental analysis, Licensing, Nuclear power plant operations
Proceedings Papers

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66463
https://doi.org/10.1115/ICONE25-66463
View Paper titled, Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System
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Topics: Experimental analysis, Hydraulic drive systems, Cylinders, Temperature, Flow (Dynamics), Scram, Blades, Design, Dynamics (Mechanics), Fuels
Proceedings Papers

Investigation of Thermohydraulic Models for Condensation and Boiling in Passive Safety Systems

Frances Viereckl, R. Manthey, C. Schuster, A. Hurtado
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A045, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67327
https://doi.org/10.1115/ICONE25-67327
View Paper titled, Investigation of Thermohydraulic Models for Condensation and Boiling in Passive Safety Systems
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Topics: Boiling, Condensation, Safety, Heat transfer, Heat, Chain, Condensed matter, Condensers (steam plant), Containment, Flow (Dynamics)
Proceedings Papers

RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure

Ikuo Kinoshita, Toshihide Torige
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A035, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60525
https://doi.org/10.1115/ICONE24-60525
View Paper titled, RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure
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Topics: Accident management, Boilers, Uncertainty analysis, Uncertainty, Accidents, Cladding systems (Building), Coolants, Experimental analysis, High pressure (Physics), Reliability
Proceedings Papers

Thermal-Hydraulic Investigations to the Flow of Model Gases at a PWR Fuel Assembly Dummy and Overflow of Air Above the Top of the Dummy

H. Chahi, W. Kästner, S. Alt
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A077, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61007
https://doi.org/10.1115/ICONE24-61007
View Paper titled, Thermal-Hydraulic Investigations to the Flow of Model Gases at a PWR Fuel Assembly Dummy and Overflow of Air Above the Top of the Dummy
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Topics: Flow (Dynamics), Fuels, Gases, Manufacturing, Pressurized water reactors, Storage, Steam, Modeling, Safety, Simulation
Proceedings Papers

SIMMER-III Code Assessment for Material Expansion Dynamics During Core Disruptive Accidents in Sodium-Cooled Fast Reactors

Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A033, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30281
https://doi.org/10.1115/ICONE22-30281
View Paper titled, SIMMER-III Code Assessment for Material Expansion Dynamics During Core Disruptive Accidents in Sodium-Cooled Fast Reactors
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Topics: Accidents, Dynamics (Mechanics), Sodium fast reactors, Safety, Bubbles, Computers, Coolants, Experimental analysis, Multiphase flow, Vapors
Proceedings Papers

Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum: (4) Multi-Channel Experimental Analysis by Detailed Two-Phase Analysis Code TPFIT

Takayuki Suzuki, Hiroyuki Yoshida, Fumihisa Nagase, Yutaka Abe, Akiko Kaneko
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30154
https://doi.org/10.1115/ICONE22-30154
View Paper titled, Development of Numerical Simulation for Jet Breakup Behavior in Complicated Structure of BWR Lower Plenum: (4) Multi-Channel Experimental Analysis by Detailed Two-Phase Analysis Code TPFIT
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Topics: Boiling water reactors, Computer simulation, Experimental analysis, Simulation, Accidents, Flow (Dynamics), Shapes, Computational fluid dynamics, Evaluation methods, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Analysis of the Velocity Field of Thermal Stratification in Pipes

Limiao Xing, Wenbin Zhuo, Bingde Chen, Dewen Yuan, Wanyu Xiong
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A082, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16265
https://doi.org/10.1115/ICONE21-16265
View Paper titled, Analysis of the Velocity Field of Thermal Stratification in Pipes
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Topics: Pipes, Thermal stratification, Flow (Dynamics), Temperature, Fluids, Computational fluid dynamics, Stress, Surges, Damage, Deformation
Proceedings Papers

Experimental Analyses by SIMMER-III on Duct-Wall Failure and Fuel Discharge/Relocation Behavior

Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A008, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15163
https://doi.org/10.1115/ICONE21-15163
View Paper titled, Experimental Analyses by SIMMER-III on Duct-Wall Failure and Fuel Discharge/Relocation Behavior
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Topics: Ducts, Experimental analysis, Failure, Fuels, Coolants, Accidents, Boiling, Computers, Fluid dynamics, Melting
Proceedings Papers

Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III

Bin Zhang, Tatsuya Matsumoto, Koji Morita, Hidemasa Yamano, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 751-760, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54684
https://doi.org/10.1115/ICONE20-POWER2012-54684
View Paper titled, Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III
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Topics: Computer simulation, Particulate matter, Sodium, Accidents, Boiling, Convection, Experimental analysis, Fast neutron reactors, Fluidization, Heat
Proceedings Papers

Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management

Valery G. Sidorov, Vladimir Bezlepkin, Sergej Alekseev, Sergey Semashko, Igor Ivkov, Vladimir Kukhtevich
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 589-596, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29857
https://doi.org/10.1115/ICONE18-29857
View Paper titled, Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management
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Topics: Accident management, Accidents, Boilers, Circuits, Containment, Cooling, Design, Electricity (Physics), Emissions, Experimental analysis
Proceedings Papers

Validation of a New Lattice Physics Code GALAXY for PWRs

Kazuya Yamaji, Hiroki Koike, Daisuke Sato, Shinobu Tsubota, Hideki Matsumoto
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 27-34, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29221
https://doi.org/10.1115/ICONE18-29221
View Paper titled, Validation of a New Lattice Physics Code GALAXY for PWRs
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Topics: Physics, Pressurized water reactors, Computational methods, Experimental analysis, Irradiation (Radiation exposure), Manufacturing, Nuclear design
Proceedings Papers

Experimental Analyses by SIMMER-III on Debris-Bed Coolability and Metallic Fuel Freezing Behavior

Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 281-290, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29296
https://doi.org/10.1115/ICONE18-29296
View Paper titled, Experimental Analyses by SIMMER-III on Debris-Bed Coolability and Metallic Fuel Freezing Behavior
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Topics: Experimental analysis, Freezing, Fuels, Accidents, Boiling, Cladding systems (Building), Computers, Databases, Fluid dynamics, Heat conduction
Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 389-398, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75462
https://doi.org/10.1115/ICONE17-75462
View Paper titled, Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion
Open the PDF for Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion in another window
Topics: Experimental analysis, Fuels, Safety, Sodium fast reactors, Failure, Accidents, Computers, Databases, Deformation, Failure mechanisms
Proceedings Papers

Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses

Yuichi Yamamoto, Etsujo Hirano, Masaya Oue, Sensuke Shimizu, Noriyuki Shirakawa, Seiichi Koshizuka, Koji Morita, Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 409-418, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75521
https://doi.org/10.1115/ICONE17-75521
View Paper titled, Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses
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Topics: Experimental analysis, Safety, Sodium fast reactors, Thermal hydraulics, Accidents, Computers, Conceptual design, Particulate matter, Physics
Proceedings Papers

Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation

Ikuo Kinoshita, Hiroichi Nagumo, Minoru Yamada, Yasuhiro Sasaki, Yoshitaka Yoshida
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 611-621, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75550
https://doi.org/10.1115/ICONE17-75550
View Paper titled, Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation
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Topics: Uncertainty, Heat transfer, Condensation, Cooling, Flow (Dynamics), Safety, Stratified flow, Water, Boilers, Boiling
Proceedings Papers

R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS

Hidemasa Yamano, Yoshiharu Tobita
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 307-314, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48385
https://doi.org/10.1115/ICONE16-48385
View Paper titled, R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS
Open the PDF for R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS in another window
Topics: Experimental analysis, Fast neutron reactors, Safety, Scientific computing, Fuels, Steel, Boiling, Freezing, Accidents, Boundary-value problems