1-17 of 17
Thermal Hydraulics of Advanced Nuclear Reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Study on the Flow Distribution Around a Bathtub Vortex in a Cylindrical Vessel

S. Sakai, H. Madarame, K. Okamoto
Proc. ASME. IMECE97, Nuclear Engineering, 81-86, November 16–21, 1997
Paper No: IMECE1997-0610
https://doi.org/10.1115/IMECE1997-0610
View Paper titled, Study on the Flow Distribution Around a Bathtub Vortex in a Cylindrical Vessel
Open the PDF for Study on the Flow Distribution Around a Bathtub Vortex in a Cylindrical Vessel in another window
Topics: Flow (Dynamics), Vessels, Vortices, Inks, Lasers, Open channels (Hydraulics), Particulate matter, Pipes, Velocimeters
Proceedings Papers

Simulation of Some Emergency Operating Procedure for VVER-440 Reactors

József Bánáti, György Ézsöl
Proc. ASME. IMECE97, Nuclear Engineering, 57-64, November 16–21, 1997
Paper No: IMECE1997-0607
https://doi.org/10.1115/IMECE1997-0607
View Paper titled, Simulation of Some Emergency Operating Procedure for VVER-440 Reactors
Open the PDF for Simulation of Some Emergency Operating Procedure for VVER-440 Reactors in another window
Topics: Emergencies, Simulation, Nuclear power stations, Safety, Accident management, Circuits, Computer simulation, Modeling, Pressure, Transients (Dynamics)
Proceedings Papers

Condensation Enhancement on a Pool Surface Caused by a Submerged Liquid Jet

Rex W. Shumway
Proc. ASME. IMECE97, Nuclear Engineering, 3-13, November 16–21, 1997
Paper No: IMECE1997-0602
https://doi.org/10.1115/IMECE1997-0602
View Paper titled, Condensation Enhancement on a Pool Surface Caused by a Submerged Liquid Jet
Open the PDF for Condensation Enhancement on a Pool Surface Caused by a Submerged Liquid Jet in another window
Topics: Condensation, Pipes, Steam, Water, Accidents, Boilers, Computer software, Coolants, Heat, Nuclear design
Proceedings Papers

Features of the Calculational Method at Fluid Flow Modelling

Gregor Černe, Stojan Petelin
Proc. ASME. IMECE97, Nuclear Engineering, 35-40, November 16–21, 1997
Paper No: IMECE1997-0604
https://doi.org/10.1115/IMECE1997-0604
View Paper titled, Features of the Calculational Method at Fluid Flow Modelling
Open the PDF for Features of the Calculational Method at Fluid Flow Modelling in another window
Topics: Boundary-value problems, Density, Flow (Dynamics), Fluid dynamics, Incompressible fluids, Modeling, Navier-Stokes equations, Partial differential equations, Pressure, Reynolds number
Proceedings Papers

Data Transfer From BETHSY 9.1B Experiment to Real NPP

Stojan Petelin, Borut Mavko, Igor Ravnikar, Yassin A. Hassan
Proc. ASME. IMECE97, Nuclear Engineering, 71-80, November 16–21, 1997
Paper No: IMECE1997-0609
https://doi.org/10.1115/IMECE1997-0609
View Paper titled, Data Transfer From BETHSY 9.1B Experiment to Real NPP
Open the PDF for Data Transfer From BETHSY 9.1B Experiment to Real NPP in another window
Topics: Nuclear power stations, Transients (Dynamics), Cooling systems, Engineering standards, Heat, Simulation, Test facilities
Proceedings Papers

Bubbly Flow Identification Using Particle Image Velocimetry

Y. A. Hassan, William Schmidl, J. Ortiz-Villafuerte
Proc. ASME. IMECE97, Nuclear Engineering, 51-56, November 16–21, 1997
Paper No: IMECE1997-0606
https://doi.org/10.1115/IMECE1997-0606
View Paper titled, Bubbly Flow Identification Using Particle Image Velocimetry
Open the PDF for Bubbly Flow Identification Using Particle Image Velocimetry in another window
Topics: Bubbly flow, Particulate matter, Bubbles, Shapes, Acoustics, Flow visualization, Helicopters, Lasers, Pipe flow, Waves
Proceedings Papers

Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis

Jinzhao Zhang, S. M. Bajorek, R. M. Kemper, M. E. Nissley, N. Petkov, L. E. Hochreiter
Proc. ASME. IMECE97, Nuclear Engineering, 15-33, November 16–21, 1997
Paper No: IMECE1997-0603
https://doi.org/10.1115/IMECE1997-0603
View Paper titled, Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis
Open the PDF for Application of the W COBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA Analysis in another window
Topics: Accidents, Approximation, Boundary-value problems, Cladding systems (Building), Coolants, Cooling, Design, Emergency core cooling systems, Film boiling, Heat transfer
Proceedings Papers

Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA

Stojan Petelin, Borut Mavko, Mihael Jurkovic
Proc. ASME. IMECE97, Nuclear Engineering, 41-50, November 16–21, 1997
Paper No: IMECE1997-0605
https://doi.org/10.1115/IMECE1997-0605
View Paper titled, Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA
Open the PDF for Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA in another window
Topics: Boilers, Coolants, Nuclear power stations, Transients (Dynamics)
Proceedings Papers

Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head

R. E. Schwirian
Proc. ASME. IMECE97, Nuclear Engineering, 65-70, November 16–21, 1997
Paper No: IMECE1997-0608
https://doi.org/10.1115/IMECE1997-0608
View Paper titled, Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head
Open the PDF for Computational Fluid Dynamics Analysis of Thermal Mixing in the AP600 Upper Head in another window
Topics: Buoyancy, Computational fluid dynamics, Coolants, Pressurized water reactors, Stress, Temperature profiles, Transients (Dynamics)
Proceedings Papers

An Experimental Correlation of Quenching Temperature Under Top-Down Reflooding in a Vertical Tube

Yanping Huang, Xuemei Lang, Bingde Chen
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 283-288, November 14–19, 1999
Paper No: IMECE1999-1129
https://doi.org/10.1115/IMECE1999-1129
View Paper titled, An Experimental Correlation of Quenching Temperature Under Top-Down Reflooding in a Vertical Tube
Open the PDF for An Experimental Correlation of Quenching Temperature Under Top-Down Reflooding in a Vertical Tube in another window
Topics: Quenching (Metalworking), Temperature, Flow (Dynamics), Pressure, Dimensions, Subcooling, Transients (Dynamics)
Proceedings Papers

Thermal Margin Evaluation for FELI Fuel Assemblies During an Accidental Vessel Draining

Richard G. Ambrosek, Fred W. Ingram, Grant L. Hawkes, Jim W. Sterbentz
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 275-282, November 14–19, 1999
Paper No: IMECE1999-1128
https://doi.org/10.1115/IMECE1999-1128
View Paper titled, Thermal Margin Evaluation for FELI Fuel Assemblies During an Accidental Vessel Draining
Open the PDF for Thermal Margin Evaluation for FELI Fuel Assemblies During an Accidental Vessel Draining in another window
Topics: Drainage, Fuels, Vessels, Cladding systems (Building), Computer software, Coolants, Cooling, Finite element analysis, Heat transfer coefficients, Heating
Proceedings Papers

Measurement of the Thermal and Velocity Fields in the Liquid Phase of Turbulent Subcooled Bubbly Boiling Flow

R. P. Roy, S. Kang, J. A. Zarate
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 317-324, November 14–19, 1999
Paper No: IMECE1999-1133
https://doi.org/10.1115/IMECE1999-1133
View Paper titled, Measurement of the Thermal and Velocity Fields in the Liquid Phase of Turbulent Subcooled Bubbly Boiling Flow
Open the PDF for Measurement of the Thermal and Velocity Fields in the Liquid Phase of Turbulent Subcooled Bubbly Boiling Flow in another window
Topics: Boiling, Flow (Dynamics), Subcooling, Turbulence, Wire, Temperature, Circuits, Dimensions, Fluids, Lasers
Proceedings Papers

Experimental Laboratory Research on Computer-Aided System for Determining Fluid Flow Patterns in Air-Water Two-Phase Flow

Jerry K. Keska, Michael D. Smith, Quinn F. Dolan
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 305-315, November 14–19, 1999
Paper No: IMECE1999-1132
https://doi.org/10.1115/IMECE1999-1132
View Paper titled, Experimental Laboratory Research on Computer-Aided System for Determining Fluid Flow Patterns in Air-Water Two-Phase Flow
Open the PDF for Experimental Laboratory Research on Computer-Aided System for Determining Fluid Flow Patterns in Air-Water Two-Phase Flow in another window
Topics: Computer-aided engineering, Fluid dynamics, Two-phase flow, Water, Flow (Dynamics), Computers, Measurement systems, Heat exchangers, Mass transfer, Sensors
Proceedings Papers

Experimental Study of the Transient Turbulence Generated by a Bubble Using PIV

Javier Ortiz-Villafuerte, William D. Schmidl, Yassin A. Hassan
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 297-304, November 14–19, 1999
Paper No: IMECE1999-1131
https://doi.org/10.1115/IMECE1999-1131
View Paper titled, Experimental Study of the Transient Turbulence Generated by a Bubble Using PIV
Open the PDF for Experimental Study of the Transient Turbulence Generated by a Bubble Using PIV in another window
Topics: Bubbles, Transients (Dynamics), Turbulence, Pipes, Flow (Dynamics), Particulate matter, Water
Proceedings Papers

A Method for Estimating Acoustic Implosion Efficiencies for Collapsing Cavities in Nuclear Reactor Systems

C. M. Kullberg
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 289-295, November 14–19, 1999
Paper No: IMECE1999-1130
https://doi.org/10.1115/IMECE1999-1130
View Paper titled, A Method for Estimating Acoustic Implosion Efficiencies for Collapsing Cavities in Nuclear Reactor Systems
Open the PDF for A Method for Estimating Acoustic Implosion Efficiencies for Collapsing Cavities in Nuclear Reactor Systems in another window
Topics: Acoustics, Cavities, Nuclear reactors, Water hammer, Bubbles, Condensation, Damage, Nuclear industry, Pressure, Subcooling
Proceedings Papers

Safety Analyses at the Idaho National Engineering and Environmental Laboratory Test Reactor Area: Past to Present

Richard G. Ambrosek, Fred W. Ingram
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 257-265, November 14–19, 1999
Paper No: IMECE1999-1126
https://doi.org/10.1115/IMECE1999-1126
View Paper titled, Safety Analyses at the Idaho National Engineering and Environmental Laboratory Test Reactor Area: Past to Present
Open the PDF for Safety Analyses at the Idaho National Engineering and Environmental Laboratory Test Reactor Area: Past to Present in another window
Topics: Safety, Computer software, Dimensions, Errors, Modeling, Regulations
Proceedings Papers

Survey of Research Activities for Passive Safety System of AC600

Bingde Chen, Zhumao Yang, Fuyun Ji
Proc. ASME. IMECE99, Heat Transfer: Volume 4, 267-274, November 14–19, 1999
Paper No: IMECE1999-1127
https://doi.org/10.1115/IMECE1999-1127
View Paper titled, Survey of Research Activities for Passive Safety System of AC600
Open the PDF for Survey of Research Activities for Passive Safety System of AC600 in another window
Topics: Safety, Design, Containment, Cooling systems, Pressurized water reactors, Computers, Damage, Databases, Economics , Heat