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...]
Archives for September 2017
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...]
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...]
CFD Simulation of a Coolant Flow and Heat Transfer in a Pebble Bed Reactor
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...]
PIV Measurements of Jet Flow Mixing in the Vicinity of Rod Bundles using Matched Refractive Index
Citation: N. Amini, E. Dominquez-Ontiveros, C. Estrada-Perez, S. Fortenberry, Y. A. Hassan PIV Measurements of Jet Flow Mixing in the Vicinity of Rod Bundles using Matched Refractive Index Presented at the 16th International Conference on Nuclear Engineering (ICONE16), May 11-15, 2008, Orlando, … [Read more...]
The Effect of Electric Potential on Fibrous Debris Bypass through a Containment Sump Strainer
Citation: S. Lee, R. Vaghetto, J. Lim, M. Kappes, Y. A. Hassan The Effect of Electric Potential on Fibrous Debris Bypass through a Containment Sump Strainer Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13760 2015-08-30Associated … [Read more...]
A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models
Citation: B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) … [Read more...]
MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191
Citation: B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191 Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13354. … [Read more...]
Experimental Observations of Boric Acid Precipitation Scenarios
Citation: R. Vaghetto, S. Lee, E. Kee, Y. A. Hassan Experimental Observations of Boric Acid Precipitation Scenarios Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13055. 2015-08-30 … [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...]
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...]
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 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...]
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 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...]
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...]
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...]
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...]
RELAP5-3D Simulations of the Reactor Cavity Cooling System Experimental Facility
Citation: R. Vaghetto, H. Wu, Y. A. Hassan RELAP5-3D Simulations of the Reactor Cavity Cooling System Experimental Facility Presented at 2012 ANS Annual Meeting, June 24-28, 2012, Chicago, Il and published in the ANS Transactions, Vol. 106, 2012. 2012-06-24Associated Project(s): - 1. NEUP … [Read more...]
Thermal-Hydraulic System Response of a Pressurized Water Reactor Under Full Core Blockage Hypothesis during Loss of Coolant Accidents
Citation: R. Vaghetto, D. De Luca, Y. A. Hassan Thermal-Hydraulic System Response of a Pressurized Water Reactor Under Full Core Blockage Hypothesis during Loss of Coolant Accidents International Workshop of Nuclear Safety and Severe Accident (NUSSA), September 7-8 2012, Beijing, China. 2012-09-07 … [Read more...]
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