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Proceedings Papers

CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer

Abdelgadir Eltayeb, Sichao Tan, Ayodeji A. Ala, Zhang Qi, Nisrene M. Ahmed

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A016, July 22–26, 2018

Paper No: ICONE26-82212

DOI: https://doi.org/10.1115/ICONE26-82212

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Topics: Computational fluid dynamics, Coolants, Reactor vessels, Velocity measurement, Fluid dynamics, Pressurized water reactors, Boundary-value problems, Cylinders, Engineering simulation, Flow (Dynamics)

Proceedings Papers

OECD-NEA Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation

Timothy Valentine, Kostadin Ivanov, Maria Avramova, Alessandro Petruzzi, Jean-Pascal Hudelot, Upendra Rohatgi, Kiril Velkov

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A009, July 22–26, 2018

Paper No: ICONE26-81571

DOI: https://doi.org/10.1115/ICONE26-81571

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Topics: Physics, Linkages, Modeling, Nuclear power, Simulation, Underpinning

Proceedings Papers

Stand-Alone Containment Analysis of the Phébus FPT-3 Test With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A002, July 22–26, 2018

Paper No: ICONE26-81139

DOI: https://doi.org/10.1115/ICONE26-81139

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Topics: Containment, Accidents, Aerosols, Sensitivity analysis, Computer simulation, Fuels, Pressurized water reactors, Safety, Thermal hydraulics, Transients (Dynamics)

Proceedings Papers

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Tangpei Cheng, Zeyao Mo, Chao Yang, Lili Wen, Li Deng

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A017, July 22–26, 2018

Paper No: ICONE26-82252

DOI: https://doi.org/10.1115/ICONE26-82252

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Topics: Radiation (Physics), Algorithms, Computer programming, Computers, Construction

Proceedings Papers

Validation of Film Evaporation Model in GASFLOW-MPI

Li Yabing, Zhang Han, Xiao Jianjun

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A003, July 22–26, 2018

Paper No: ICONE26-81249

DOI: https://doi.org/10.1115/ICONE26-81249

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Topics: Evaporation, Containment, Heat, Wall temperature, Air flow, Computational fluid dynamics, Cooling systems, Heating, Nuclear power stations, Safety

Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018

Paper No: ICONE26-81694

DOI: https://doi.org/10.1115/ICONE26-81694

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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

Proceedings Papers

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Stefan Radman, Carlo Fiorina, Konstantin Mikityuk, Andreas Pautz

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A018, July 22–26, 2018

Paper No: ICONE26-82260

DOI: https://doi.org/10.1115/ICONE26-82260

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Topics: Sodium fast reactors, Physics, Modeling, Geometry, Neutrons, Simulation, Testing, Thermal hydraulics

Proceedings Papers

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Run Luo, Pengfei Wang, Xinyu Wei, Shripad T. Revankar, Fuyu Zhao

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A004, July 22–26, 2018

Paper No: ICONE26-81276

DOI: https://doi.org/10.1115/ICONE26-81276

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Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation

Proceedings Papers

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Liancheng Guo, Andrei Rineiski

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A011, July 22–26, 2018

Paper No: ICONE26-81841

DOI: https://doi.org/10.1115/ICONE26-81841

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Topics: Modeling, Simulation, Accidents, Vessels, Coolants, Fuels, Sodium, Sodium fast reactors, Fast neutron reactors, Fluid dynamics

Proceedings Papers

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

Francesco D’Auria, Marco Lanfredini

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A019, July 22–26, 2018

Paper No: ICONE26-82574

DOI: https://doi.org/10.1115/ICONE26-82574

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Topics: Density, Film boiling, Flow (Dynamics), Heat flux, High pressure (Physics), Nucleate boiling, Pipes, Power density, Pressure, Temperature

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

Paper No: ICONE26-81912

DOI: https://doi.org/10.1115/ICONE26-81912

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Topics: Uncertainty analysis, Modeling, Heat losses, Internships, Uncertainty, Computer software, Contact resistance, Convection, Experimental analysis, Fuel rods

Proceedings Papers

Development and Validation of a Correlation for Wet Resuspension Simulation

Tobias Jankowski, Marco K. Koch

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A005, July 22–26, 2018

Paper No: ICONE26-81286

DOI: https://doi.org/10.1115/ICONE26-81286

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Topics: Accident management, Accidents, Aerosols, Boiling, Bubbles, Circuits, Condensed matter, Containment, Coolants, Cooling

Proceedings Papers

Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2

Jeffrey R. Kobelak, Jun Liao, Katsuhiro Ohkawa

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A020, July 22–26, 2018

Paper No: ICONE26-82610

DOI: https://doi.org/10.1115/ICONE26-82610

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Topics: Simulation, Water, Superheating, Reactor vessels, Accidents, Pressurized water reactors, Test facilities, Transients (Dynamics), Boiling, Coolants

Proceedings Papers

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Ji Soo Ahn, Michael Bluck, Matthew Eaton, Chris Jackson

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A006, July 22–26, 2018

Paper No: ICONE26-81424

DOI: https://doi.org/10.1115/ICONE26-81424

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Topics: Nuclear power stations, Thermal stratification, Pipes, Surges, Computational fluid dynamics, Cooling, Errors, Feedwater, Junctions, Piping systems

Proceedings Papers

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Fei Chao, Jianqiang Shan, Junli Gou, Pan Wu, Li Ge

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A013, July 22–26, 2018

Paper No: ICONE26-81942

DOI: https://doi.org/10.1115/ICONE26-81942

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Topics: Fluids, Pressure, Water, Gravity (Force), Diffusion (Physics), Flow (Dynamics), Waves, Algorithms, Drag (Fluid dynamics), Pressure gradient

Proceedings Papers

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Christopher Bennett, Scott Adams, Nick Alexander

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A021, July 22–26, 2018

Paper No: ICONE26-82628

DOI: https://doi.org/10.1115/ICONE26-82628

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Topics: Architects, Boilers, Databases, Design, Dimensions, Engineering disciplines, Nuclear power stations, Nuclear reactors, Safety, Small modular reactors

Proceedings Papers

Blind Simulations of NACIE-UP Experimental Tests by STH Codes

Nicola Forgione, Morena Angelucci, Gianluca Barone, Massimiliano Polidori, Antonio Cervone, Ivan Di Piazza, Fabio Giannetti, Pierdomenico Lorusso, Thorsten Hollands, Angel Papukchiev

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A007, July 22–26, 2018

Paper No: ICONE26-81434

DOI: https://doi.org/10.1115/ICONE26-81434

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Topics: Engineering simulation, Simulation, Computer simulation, Flow (Dynamics), Liquid metals, Performance, Pressure, Temperature, Thermal hydraulics

Proceedings Papers

Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1

Heriberto Sánchez-Mora, Carlos Chávez-Mercado, Chris Allison, Judith Hohorst

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A014, July 22–26, 2018

Paper No: ICONE26-81991

DOI: https://doi.org/10.1115/ICONE26-81991

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Topics: Accidents, Blades, Boiling water reactors, Computer software, Fuel rods, Hydrogen production, Nuclear industry, Nuclear reactors, Rods, Simulation

Proceedings Papers

The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool

Upendra Rohatgi, James Dyrda, Nicolas Soppera

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A022, July 22–26, 2018

Paper No: ICONE26-82631

DOI: https://doi.org/10.1115/ICONE26-82631

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Topics: Databases, Hydraulic drive systems, Nuclear reactors, Relational databases, Boiling water reactors, Computational fluid dynamics, Gas cooled reactors, High temperature, Instrumentation, Liquid metals

Proceedings Papers

Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method

Hongkuan Liao, Qing Li, Yingrui Yu, Yuying Hu, Lei Wu, Chenlin Wang, Jinyu Wang, Jinghui Wang, Peng Xiao

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A008, July 22–26, 2018

Paper No: ICONE26-81441

DOI: https://doi.org/10.1115/ICONE26-81441

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Topics: Sampling methods, Uncertainty analysis, Uncertainty, Nuclear design, Computer software, Approximation, Computation, Design, Economics , Modeling

NARROW

CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer

OECD-NEA Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation

Stand-Alone Containment Analysis of the Phébus FPT-3 Test With the ASTEC and the MELCOR Codes

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Validation of Film Evaporation Model in GASFLOW-MPI

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

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

Development and Validation of a Correlation for Wet Resuspension Simulation

Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method

Blind Simulations of NACIE-UP Experimental Tests by STH Codes

Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1

The International Experimental Thermal Hydraulic Systems Database (TIETHYS): A New NEA Validation Tool

Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method

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