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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
Paper No: ICONE2020-16584
DOI: https://doi.org/10.1115/ICONE2020-16584
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Topics: Accidents, Fire, Explosions, Radioisotopes, Aerosols, Model development, Nuclear power stations, Probabilistic risk assessment, Safety, Spent nuclear fuels
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
Paper No: ICONE26-81247
DOI: https://doi.org/10.1115/ICONE26-81247
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Topics: Simulation, Two-phase flow, Resolution (Optics), Bubbles, Turbulence, Algorithms, Bubbly flow, Model development, Computer simulation, Flow (Dynamics)
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
Paper No: ICONE26-81049
DOI: https://doi.org/10.1115/ICONE26-81049
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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

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
Paper No: ICONE26-82415
DOI: https://doi.org/10.1115/ICONE26-82415
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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
Paper No: ICONE26-81469
DOI: https://doi.org/10.1115/ICONE26-81469
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Topics: Design, Risk, Model development, Safety, Probabilistic risk assessment, Probabilistic safety assessment
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
Paper No: ICONE26-82503
DOI: https://doi.org/10.1115/ICONE26-82503
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Topics: Boilers, Numerical analysis, Rupture, Vessels, Pressure, Water, Coolants, Design, Flow (Dynamics), Liquid metals
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
Paper No: ICONE26-82553
DOI: https://doi.org/10.1115/ICONE26-82553
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Topics: Design, Risk, Safety, Boiling water reactors, Damage, Model development, Probabilistic safety assessment
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
Paper No: ICONE25-66391
DOI: https://doi.org/10.1115/ICONE25-66391
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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
Paper No: ICONE25-66970
DOI: https://doi.org/10.1115/ICONE25-66970
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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
Paper No: ICONE24-60425
DOI: https://doi.org/10.1115/ICONE24-60425
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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
Paper No: ICONE24-61136
DOI: https://doi.org/10.1115/ICONE24-61136
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Topics: Safety, Accidents, Computers, Coolants, Fluids, Model development, Momentum, Navier-Stokes equations, Nuclear reactor coolants, Nuclear reactors
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
Paper No: ICONE22-30568
DOI: https://doi.org/10.1115/ICONE22-30568
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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
Paper No: ICONE22-30729
DOI: https://doi.org/10.1115/ICONE22-30729
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Topics: Accidents, Spent nuclear fuels, Flow (Dynamics), Fuels, Coolants, Heat, Performance, Spent fuel storage, Boiling water reactors, Buoyancy
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
Paper No: ICONE22-30391
DOI: https://doi.org/10.1115/ICONE22-30391
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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

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
Paper No: ICONE21-16911
DOI: https://doi.org/10.1115/ICONE21-16911
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Topics: Combustion, Hydrogen, Modeling, Explosions, Accidents, Flames, Nuclear power stations, Computational fluid dynamics, Computer simulation, Databases
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
Paper No: ICONE21-16378
DOI: https://doi.org/10.1115/ICONE21-16378
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Topics: Control systems, Design, Nuclear power stations, Hardware, Simulation, Testing, Architecture, Computation, Design methodology, Engineering prototypes
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
Paper No: ICONE20-POWER2012-54087
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54087
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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

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
Paper No: ICONE20-POWER2012-54390
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54390
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Topics: Dust, Graphite, Modeling, Very high temperature reactors, Nuclear fission, Accidents, Circuits, Coolants, Hazards, Helium
Proceedings Papers

Simulation of Thermal-Hydraulic Process of Reactor in HTR-PM

Kefeng Zhou, Yangping Zhou, Yuanle Ma, Zhe Sui, Fu Li, Yujie Dong
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 187-191, May 17–21, 2010
Paper No: ICONE18-29187
DOI: https://doi.org/10.1115/ICONE18-29187
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Topics: Design, Heat transfer, Model development, Simulation, Very high temperature reactors
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
Paper No: ICONE18-29681
DOI: https://doi.org/10.1115/ICONE18-29681
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Topics: Model development, Particulate matter, Accidents, Dust, Vacuum, Carbon, Computational fluid dynamics, Dust explosions, Fittings, Flow (Dynamics)