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Proceedings Papers

Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant

Feng Chu-ran, Ma Yuan, Yan Lin, Yang Guansan, Liu Bin
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93295
https://doi.org/10.1115/ICONE29-93295
View Paper titled, Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant
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Topics: Nuclear power stations, Pressurized water reactors, Statistical analysis, Design, Damage, Decision making, Errors, Event history analysis, Failure, Model development
Proceedings Papers

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Kenneth C. Wagner, David L. Y. Louie
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A045, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16584
https://doi.org/10.1115/ICONE2020-16584
View Paper titled, MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant
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Topics: Accidents, Fire, Explosions, Radioisotopes, Aerosols, Model development, Nuclear power stations, Probabilistic risk assessment, Safety, Spent nuclear fuels
Proceedings Papers

Non-LWR Model Development for the MELCOR Code

Larry Humphries, Brad Beeny, David Louie, Hossein Esmaili, Michael Salay
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A056, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82415
https://doi.org/10.1115/ICONE26-82415
View Paper titled, Non-LWR Model Development for the MELCOR Code
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Topics: Light water reactors, Model development, Fluids, Modeling, Molten salt reactors, Sodium, Sodium fast reactors, Accidents, Graphite, Very high temperature reactors
Proceedings Papers

Development and Application of Level 3 PSA for the UK ABWR Generic Design Assessment

Elizabeth Grindon, Neil Harman, Carmen Niculae, Ming Leang Ang, Hironobu Iwanami, Tomoharu Hashimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A044, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81469
https://doi.org/10.1115/ICONE26-81469
View Paper titled, Development and Application of Level 3 PSA for the UK ABWR Generic Design Assessment
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Topics: Design, Risk, Model development, Safety, Probabilistic risk assessment, Probabilistic safety assessment
Proceedings Papers

Overview of PSA for the UK ABWR Generic Design Assessment

Naoki Hirokawa, Yuki Ishiwatari, Daisuke Taniguchi, Kohei Hisamochi
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A023, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82553
https://doi.org/10.1115/ICONE26-82553
View Paper titled, Overview of PSA for the UK ABWR Generic Design Assessment
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Topics: Design, Risk, Safety, Boiling water reactors, Damage, Model development, Probabilistic safety assessment
Proceedings Papers

Design of a Closely-Spaced Rod Bundle for a Reference Direct Numerical Simulation

Afaque Shams, Tomasz Kwiatkowski
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81049
https://doi.org/10.1115/ICONE26-81049
View Paper titled, Design of a Closely-Spaced Rod Bundle for a Reference Direct Numerical Simulation
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Topics: Computer simulation, Design, Fuel rods, Flow (Dynamics), Computational fluid dynamics, Reynolds-averaged Navier–Stokes equations, Heat transfer, Computation, Databases, Fluids
Proceedings Papers

Interface Tracking Simulations of Two-Phase Flow Utilizing Adaptive Meshing Capabilities

Joseph J. Cambareri, Igor A. Bolotnov
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81247
https://doi.org/10.1115/ICONE26-81247
View Paper titled, Interface Tracking Simulations of Two-Phase Flow Utilizing Adaptive Meshing Capabilities
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Topics: Simulation, Two-phase flow, Resolution (Optics), Bubbles, Turbulence, Algorithms, Bubbly flow, Model development, Computer simulation, Flow (Dynamics)
Proceedings Papers

Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code

Alessio Pesetti, Mariano Tarantino, Nicola Forgione
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A028, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82503
https://doi.org/10.1115/ICONE26-82503
View Paper titled, Experimental and Numerical Analysis of Steam Generator Tube Rupture Event for MYRRHA Reactor in CIRCE Facility With SIMMER-IV Code
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Topics: Boilers, Numerical analysis, Rupture, Vessels, Pressure, Water, Coolants, Design, Flow (Dynamics), Liquid metals
Proceedings Papers

Particle Deposition by Thermophoresis Under High Temperature Conditions in a Helium-Flow

Felix Fischer, Andreas Andris, Wolfgang Lippmann, Antonio Hurtado
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66391
https://doi.org/10.1115/ICONE25-66391
View Paper titled, Particle Deposition by Thermophoresis Under High Temperature Conditions in a Helium-Flow
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Topics: Flow (Dynamics), Helium, High temperature, Particulate matter, Dust, Graphite, Aerosols, Fuels, Safety, Temperature
Proceedings Papers

Development of 4S BEPU Method and Application in CAP1400 Containment Response Analysis

Liu Xin, Hu Benxue, Wang Zhe, Wang Guodong, Wang Zhangli, Zhang Di, Yang Ping
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A067, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66970
https://doi.org/10.1115/ICONE25-66970
View Paper titled, Development of 4S BEPU Method and Application in CAP1400 Containment Response Analysis
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Topics: Containment, Pressure, Uncertainty, Safety, Licensing, Sensitivity analysis, Accidents, Condensation, Coolants, Heat
Proceedings Papers

The Preliminary Experimental Study Based on Failure Mechanism of the RPV Lower Head

XianKe Meng, LiKai Fei, Aijing Zhang, SiJiang Xiong, Lei Cui, YaoDong Chen
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A025, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60425
https://doi.org/10.1115/ICONE24-60425
View Paper titled, The Preliminary Experimental Study Based on Failure Mechanism of the RPV Lower Head
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Topics: Failure mechanisms, Critical heat flux, Flow (Dynamics), Temperature, Containment vessels, Heat, Heating, Accident management, Accidents, Cavities
Proceedings Papers

A Thermal Hydraulic Phenomenon Based Review on the Validation Matrix of Several Reactor Safety Analysis Systems Codes

Jun Liao, Scott E. Fortune
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A088, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61136
https://doi.org/10.1115/ICONE24-61136
View Paper titled, A Thermal Hydraulic Phenomenon Based Review on the Validation Matrix of Several Reactor Safety Analysis Systems Codes
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Topics: Safety, Accidents, Computers, Coolants, Fluids, Model development, Momentum, Navier-Stokes equations, Nuclear reactor coolants, Nuclear reactors
Proceedings Papers

Experience Gained From the Living PSA Project for Dukovany NPP

Stanislav Hust’ák
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A014, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30391
https://doi.org/10.1115/ICONE22-30391
View Paper titled, Experience Gained From the Living PSA Project for Dukovany NPP
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Topics: Nuclear power stations, Computer software, Design, Event history analysis, Model development, Probabilistic safety assessment, Risk assessment, Risk monitoring, Risk-based decision making, Safety
Proceedings Papers

Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe

Tatsuya Yamaji, Kohei Yamazaki, Yasuo Koizumi, Hiroyasu Ohtake, Koji Hasegawa, Shota Araki, Akira Ohnuki, Hiroaki Nishi
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A043, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30568
https://doi.org/10.1115/ICONE22-30568
View Paper titled, Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe
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Topics: Boilers, Flow (Dynamics), Model development, Pipes, Water, Steam, Accidents, Coolants, Drainage, Film flow
Proceedings Papers

Spent Fuel Pool Under Severe Accident Conditions

Bernd Jaeckel, Jonathan Birchley, Leticia Fernandez-Moguel
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A029, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30729
https://doi.org/10.1115/ICONE22-30729
View Paper titled, Spent Fuel Pool Under Severe Accident Conditions
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Topics: Accidents, Spent nuclear fuels, Flow (Dynamics), Fuels, Coolants, Heat, Performance, Spent fuel storage, Boiling water reactors, Buoyancy
Proceedings Papers

Using a Hybrid FPGA-CPU Platform for a User-Friendly Environment in Control Systems Design: A Possible Application to Nuclear Plants

Mauro Cappelli, Stefano Di Gennaro, Fabrizio Memmi, Massimo Sepielli
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T13A027, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16378
https://doi.org/10.1115/ICONE21-16378
View Paper titled, Using a Hybrid FPGA-CPU Platform for a User-Friendly Environment in Control Systems Design: A Possible Application to Nuclear Plants
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Topics: Control systems, Design, Nuclear power stations, Hardware, Simulation, Testing, Architecture, Computation, Design methodology, Engineering prototypes
Proceedings Papers

Hydrogen Combustion Modelling in Large-Scale Geometries

E. Studer, A. Beccantini, S. Kudriakov, A. Velikorodny
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A030, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16911
https://doi.org/10.1115/ICONE21-16911
View Paper titled, Hydrogen Combustion Modelling in Large-Scale Geometries
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Topics: Combustion, Hydrogen, Modeling, Explosions, Accidents, Flames, Nuclear power stations, Computational fluid dynamics, Computer simulation, Databases
Proceedings Papers

Development of Modeling Transport of Graphite Dust in HTGR During Normal Operation Condition

Zhipeng Chen, Fei Xie, Yanhua Zheng, Lei Shi, Fu Li
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 291-297, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54390
https://doi.org/10.1115/ICONE20-POWER2012-54390
View Paper titled, Development of Modeling Transport of Graphite Dust in HTGR During Normal Operation Condition
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Topics: Dust, Graphite, Modeling, Very high temperature reactors, Nuclear fission, Accidents, Circuits, Coolants, Hazards, Helium
Proceedings Papers

CFD Model Development and Validation for VHTR Air Ingress Scenarios

J. Baggemann, S. Kelm, H.-J. Allelein, A. Hurtado
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 383-392, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54087
https://doi.org/10.1115/ICONE20-POWER2012-54087
View Paper titled, CFD Model Development and Validation for VHTR Air Ingress Scenarios
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Topics: Computational fluid dynamics, Model development, Very high temperature reactors, Accidents, Boundary-value problems, Databases, Fluids, High temperature, Nuclear environmental management, Porous materials
Proceedings Papers

Solid Particle Resuspension Model Development for the GASFLOW Code

Zhanjie Xu, John R. Travis, Thomas Jordan
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 511-517, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29681
https://doi.org/10.1115/ICONE18-29681
View Paper titled, Solid Particle Resuspension Model Development for the GASFLOW Code
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Topics: Model development, Particulate matter, Accidents, Dust, Vacuum, Carbon, Computational fluid dynamics, Dust explosions, Fittings, Flow (Dynamics)