Citation: W. K. In, Y. A. Hassan CFD Simulation of a Coolant Flow and Heat Transfer in a Pebble Bed Reactor International Topical Meeting on High Temperature Reactor Technology, September 28-October 1, 2008, Washington, DC, USA and published in the conference proceedings, HTR2008-58334, 2008. … [Read more...]
Numerical Simulations of Jet Flow Mixing within Rod Bundles
Citation: N. O. Salpeter, Y. A. Hassan Numerical Simulations of Jet Flow Mixing within Rod Bundles presented at International Topical Meeting on High Temperature Reactor Technology, September 28-October 1, 2008, Washington, DC, USA and published in the conference proceedings, HTR2008-58321, 2008 … [Read more...]
Measurements of Flow Modification by Particle Deposition inside a Packed Bed Using Time-Resolved PIV
Citation: E. Dominguez-Ontiveros, C. Estrada-Perez, Y. A. Hassan Measurements of Flow Modification by Particle Deposition inside a Packed Bed Using Time-Resolved PIV presented at the International Topical Meeting on High Temperature Reactor Technology, September 28-October 1, 2008, Washington, DC, … [Read more...]
An Immersed Boundary Lattice Boltzmann Method for Large Particle Sedimentation
Citation: S. Kang, Y. A. Hassan An Immersed Boundary Lattice Boltzmann Method for Large Particle Sedimentation presented at the 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations, and Safety (NUTHOS 7), Seoul, Korea, October 2008 and published in the conference … [Read more...]
Microfluidic Investigation of Diffusion Enhancement in Nanoparticle Suspensions
Citation: S. Ozturk, Y. A. Hassan, V. Ugaz Microfluidic Investigation of Diffusion Enhancement in Nanoparticle Suspensions Presented at the ECI International Conference on Heat Transfer and Fluid Flow in Microscale, Whistler, BC, Canada, September 21-26, 2008 and Published in the Conference … [Read more...]
Analysis of Thermal-Hydraulic System Response of a Pressurized Water Reactor during Hypothetical Core Blockage Scenarios
Citation: R. Vaghetto, D. De Luca, Y. A. Hassan Analysis of Thermal-Hydraulic System Response of a Pressurized Water Reactor during Hypothetical Core Blockage Scenarios The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Convention Hall, Pisa, Italy - May 12-17 … [Read more...]
The Steady-State Phase of the Reactor Cavity Cooling System Experimental Facility and Comparison with RELAP5-3D Simulations
Citation: R. Vaghetto, Y. A. Hassan The Steady-State Phase of the Reactor Cavity Cooling System Experimental Facility and Comparison with RELAP5-3D Simulations The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Convention Hall, Pisa, Italy - May 12-17 2013. … [Read more...]
Sensitivity Analysis of a Typical Large, Dry Containment Response during a Loss of Coolant Accident using RELAP5-3D and MELCOR
Citation: R. Vaghetto, B. A. Beeny, Y. A. Hassan, K. Vierow Sensitivity Analysis of a Typical Large, Dry Containment Response during a Loss of Coolant Accident using RELAP5-3D and MELCOR American Nuclear Society 2013 Annual Meeting, June 16-20 2013, Atlanta, GA. 2013-06-16 … [Read more...]
Sensitivity Study of Hypothetical Debris-Generated Core Blockage Scenarios
Citation: R. Vaghetto, A. Franklin, Y. A. Hassan Sensitivity Study of Hypothetical Debris-Generated Core Blockage Scenarios American Nuclear Society 2013 Winter Meeting and Nuclear Technology Expo, November 10-14 2013, Washington, D.C. (2013). 2013-11-10 … [Read more...]
RELAP5-3D Simulation of Core Flow Paths during a Hypothetical Debris-Generated Core Blockage Scenario
Citation: R. Vaghetto, E. Kee, Y. A. Hassan RELAP5-3D Simulation of Core Flow Paths during a Hypothetical Debris-Generated Core Blockage Scenario American Nuclear Society 2013 Winter Meeting and Nuclear Technology Expo, November 10-14 2013, Washington, D.C. (2013). 2013-11-10 … [Read more...]
Sensitivity Analysis of a Pressure Response of a Typical Large, Dry, Containment during a Double-Ended Guillotine Break LOCA Using RELAP5-3D and MELCOR
Citation: R. Vaghetto, A. Franklin, A. Vanni, Y. A. Hassan Sensitivity Analysis of a Pressure Response of a Typical Large, Dry, Containment during a Double-Ended Guillotine Break LOCA Using RELAP5-3D and MELCOR Proceedings of the 2014 ANS Annual Meeting, Reno, NV June 15-19 (2014). 2014-06-15 … [Read more...]
Sensitivity Analysis of a PWR Response during a Loss of Coolant Accident Under Hypothetical Core Blockage Scenario Using RELAP5-3D
Citation: T. Crook, R. Vaghetto, A. Vanni, Y. A. Hassan Sensitivity Analysis of a PWR Response during a Loss of Coolant Accident Under Hypothetical Core Blockage Scenario Using RELAP5-3D Proceedings of the 22nd International Conference on Nuclear Engineering, ICONE22 July 7-11, 2014, Prague, Czech … [Read more...]
Sensitivity Analysis of a PWR Containment during a Loss of Coolant Accident Using RELAP5-3D
Citation: R. Vaghetto, A. Franklin, A. Vanni, Y. A. Hassan Sensitivity Analysis of a PWR Containment during a Loss of Coolant Accident Using RELAP5-3D Proceedings of the 22nd International Conference on Nuclear Engineering, ICONE22 July 7-11, 2014, Prague, Czech Republic. 2014-07-07 … [Read more...]
Effects of Manual Operation during a Loss-of-Coolant Accident with Pump Unavailability
Citation: T. Crook, R. Vaghetto, Y. A. Hassan Effects of Manual Operation during a Loss-of-Coolant Accident with Pump Unavailability Proceedings of the 2015 American Nuclear Society Conference Annual Meeting, San Antonio, TX, June 7-11, 2015. 2015-07-07 … [Read more...]
Reactor Cavity Cooling System Experimental Facility Shakedown and RELAP5-3D Model Validation
Citation: R. Vaghetto, S. Lee, Y. A. Hassan Reactor Cavity Cooling System Experimental Facility Shakedown and RELAP5-3D Model Validation Proceedings of the 20th International Conference on Nuclear Engineering, ICONE20 July 30-August 3, 2012, Anaheim, California. 2012-07-30Associated Project(s): - … [Read more...]
Graphite Dispersion Effects Experimental Analysis for a Reactor Cavity Cooling System (RCCS)
Citation: L. Capone, R. Vaghetto, Y. A. Hassan Graphite Dispersion Effects Experimental Analysis for a Reactor Cavity Cooling System (RCCS) American Nuclear Society 2010 Winter Meeting, Novemeber 7-11 2010, Las Vegas Nv. 2010-11-07Associated Project(s): - 1. NEUP … [Read more...]
Analysis of the Thermo-hydraulic Behavior of the New TEXAS A&M RCCS Experimental Facility Using Relap5-3D
Citation: R. Vaghetto, Y. A. Hassan Analysis of the Thermo-hydraulic Behavior of the New TEXAS A&M RCCS Experimental Facility Using Relap5-3D Proceedings of ICONE19, 19th International Conference on Nuclear Engineering, May 16-19, 2011, Chiba, Japan. ICONE19-43266. 2011-05-16Associated … [Read more...]
Modeling the Modular High Temperature Gas-Cooled Reactor Core with RELAP5-3D
Citation: R. Vaghetto, P. D. Bayless, R. R. Schultz, Y. A. Hassan Modeling the Modular High Temperature Gas-Cooled Reactor Core with RELAP5-3D Proceedings of ICONE19, 19th International Conference on Nuclear Engineering, May 16-19, 2011, Chiba, Japan. ICONE19-43261. 2011-05-16 … [Read more...]
Experimental Analysis of the Effects of the Graphite Dispersion on the Thermal-Hydraulic Phenomena Inside the Reactor Cavity Cooling System
Citation: L. Capone, R. Vaghetto, Y. A. Hassan Experimental Analysis of the Effects of the Graphite Dispersion on the Thermal-Hydraulic Phenomena Inside the Reactor Cavity Cooling System Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011, Paper 11471. 2011-05-02Associated Project(s): - 1. NEUP … [Read more...]
Simulation of a Simple RCCS Experiment with RELAP5-3D System Code and Computational Fuid Dynamics Computer Program
Citation: R. Vaghetto, H. Wei, Y. A. Hassan Simulation of a Simple RCCS Experiment with RELAP5-3D System Code and Computational Fuid Dynamics Computer Program 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Ontario, Canada, September 25-30, 2011. … [Read more...]
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