Citation: R. Vaghetto, Y. A. Hassan Study of debris-generated core blockage scenarios during loss of coolant accidents using RELAP5-3D Nuclear Engineering and Design, Vol. 261, pp. 144-155, 2013. 2013-08-01Associated Project(s): … [Read more...]
Reactor cavity cooling system (RCCS) experimental characterization
Citation: L. Capone, Y. A. Hassan, R. Vaghetto Reactor cavity cooling system (RCCS) experimental characterization Nuclear Engineering and Design, Vol. 241, pp. 4775-4782, 2011. 2011-12-01Associated Project(s): … [Read more...]
Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System
Citation: R. Vaghetto, L. Capone, Y. A. Hassan Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System Nuclear Technology, Vol. 177, pp. 217-230, 2012. 2012-02-01Associated Project(s): … [Read more...]
Rheological characterization of buffered boric acid aqueous solutions in light water reactors
Citation: Yassin A. Hassan, Serdar Osturk, and Saya Lee Rheological characterization of buffered boric acid aqueous solutions in light water reactors Progress in Nuclear Engineering, Vol. 85, pp. 239-253, 2015. 2015-11-01Associated Project(s): … [Read more...]
Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor
Citation: K. L. McVay, J. H. Park, S. Lee, Y. A. Hassan, and N. K. Anand Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor Progress in Nuclear Engineering, Vol. 83, pp. 305-317, 2015. 2015-08-01Associated Project(s): … [Read more...]
Experimental study of head loss through an LOCA-generated fibrous debris bed deposited on a sump strainer for Generic Safety Issue 191
Citation: S. Lee, Y. A. Hassan, S. S. Abdulsattar, and R. Vaghetto Experimental study of head loss through an LOCA-generated fibrous debris bed deposited on a sump strainer for Generic Safety Issue 191 Progress in Nuclear Engineering, Vol. 74, pp. 166-175, 2014. 2014-07-01Associated Project(s): … [Read more...]
Permeability and compression of fibrous porous media generated from dilute suspensions of fiberglass debris during a loss of coolant accident
Citation: S. Lee, S. S. Abdulsattar, R. Vaghetto, Y. A. Hassan Permeability and compression of fibrous porous media generated from dilute suspensions of fiberglass debris during a loss of coolant accident Nuclear Engineering and Design, Vol. 291, pp. 244-260, 2015. 2015-09-01Associated Project(s): … [Read more...]
Wire-Wrapped Fuel Rod Mesh Sensitivity Study
Citation: L. M. Brockmeyer, F. S. Sarikurt, Y. A. Hassan Wire-Wrapped Fuel Rod Mesh Sensitivity Study Transactions of the American Nuclear Society 112 (1), 937-939 2015-06-10Associated Project(s): - 1. NEAMS … [Read more...]
Direct Numerical Simulation of Turbulent Flow in the Neat Wall Region of a Pebble Bed
Citation: L. H. Fick, E. Merzari, Y. A. Hassan Direct Numerical Simulation of Turbulent Flow in the Neat Wall Region of a Pebble Bed Transactions of the American Nuclear Society 112 (1), 947-950 2015-06-10Associated Project(s): - 1. NEAMS … [Read more...]
CFD Benchmark Study for Modeling of Hydrogen Distribution in the Containment
Citation: F. S. Sarikurt, Y. A. Hassan CFD Benchmark Study for Modeling of Hydrogen Distribution in the Containment Transactions of the American Nuclear Society 112 (1), 871-874. 2015-06-10 … [Read more...]
Development of a CFD Model for Pressure Drop Estimation of Molten Salts in a Crossflow Tube Bundle
Citation: L. B. Carasik, J. W. Clayton, Y. A. Hassan Development of a CFD Model for Pressure Drop Estimation of Molten Salts in a Crossflow Tube Bundle Transactions of the American Nuclear Society 112 (1), 944-946. 2015-06-10 … [Read more...]
Hydraulic Benchmark Data for PWR Mixing Vane Grid
Citation: M. Conner, Y. A. Hassan, E. Dominguez-Ontiveros Hydraulic Benchmark Data for PWR Mixing Vane Grid Nuclear Engineering and Design, Vol. 264, pp. 97-102, 2013. 2013-05-15Associated Project(s): … [Read more...]
Evaluation of Instantaneous Pressure Measurements in a 5 x 5 Rod Bundle
Citation: N. C. Galegar, E. E. Dominguez, Y. A. Hassan, M. E. Conner Evaluation of Instantaneous Pressure Measurements in a 5 x 5 Rod Bundle American Nuclear Society 2014 Winter Meeting and Technology Expo, Anaheim, California, 9-13 November 2014. 2014-11-11Associated Project(s): … [Read more...]
Turbulence Intensity and Pressure Fluctuations Experienced Downstream of a Mixing Grid
Citation: N. C. Galegar, E. E. Dominguez, Y. A. Hassan Turbulence Intensity and Pressure Fluctuations Experienced Downstream of a Mixing Grid Transactions of the American Nuclear Society 110 (1), 665-668. 2014-06-16Associated Project(s): … [Read more...]
Estimate of Development Length for Large Eddy Simulations of a Turbulent Thermal Jet
Citation: L. B. Carasik, F. Sebilleau, S. P. Walker, Y. A. Hassan Estimate of Development Length for Large Eddy Simulations of a Turbulent Thermal Jet American Nuclear Society 2014 Winter Meeting and Technology Expo, Anaheim, California, 9-13 November 2014. 2014-11-11Associated Project(s): … [Read more...]
CFD Simulations of Thermal Stratification in a Large Enclosure
Citation: L. B. Carasik, A. E. Ruggles, S. A. Walker CFD Simulations of Thermal Stratification in a Large Enclosure International Congress on Advances in Nuclear Power Plants (ICAPP) 2014 vol. 2, 1350-1359. 2014-04-09Associated Project(s): … [Read more...]
Preliminary Investigation of Turbulent Flow Behavior of 3-D Twin Jets using CFD Analysis
Citation: L. B. Carasik, A. E. Ruggles, Y. A. Hassan Preliminary Investigation of Turbulent Flow Behavior of 3-D Twin Jets using CFD Analysis Transactions of the American Nuclear Society 110 (1), 689-692. 2014-06-18Associated Project(s): … [Read more...]
Experimental Study of a Simplified 3×3 Rod Bundle Using DPTV
Citation: E. Dominguez-Ontiveros, Y. A. Hassan Experimental Study of a Simplified 3x3 Rod Bundle Using DPTV Nuclear Engineering and Design, Vol. 279, pp. 50-59, 2014. 2014-09-01 … [Read more...]
GSI-191
Short Summary:The thermal-hydraulic team has actively contributed to the Generic Safety Issue (GSI) 191 resolution project, developing computational and experimental capabilities and supporting the nuclear power industry with thermal-hydraulic analyses of different aspects of the issue.Abstract:The … [Read more...]
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