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...]
Archives for October 2017
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...]
Analysis of Long-Term Cooling of a LOCA by Coupling RELAP5-3D and MELCOR
Citation: R. Vaghetto, B. A. Beeny, Y. A. Hassan, K. Vierow Analysis of Long-Term Cooling of a LOCA by Coupling RELAP5-3D and MELCOR American Nuclear Society 2012 Winter Meeting and Nuclear Technology Expo, November 11-15 2012, San Diego, CA. 2012-11-11 … [Read more...]
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