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...]
Archives for 2017
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...]
Steam Condensation Test Facility
The steam-air condensation facility investigates the phenomena of direct contact condensation that occurs when steam comes in direct contact with water creating a violent and complicated exchange of mass and energy. The heat transfer coefficient between the steam and water is calculated, as well as … [Read more...]
Evaluation and Testing of HTGR Reactor Building Response to Depressurization Accidents
The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR). During accident conditions (depressurized loss of forced cooling, D-LOFC) air may enter into the reactor pressure vessel as a result of a break in the helium … [Read more...]
Critical Heat Flux Test Facility
The Critical Heat Flux / Departure from Nucleate Boiling test loop provides a means of evaluating the DNB performance of test geometries representative of commercial pressurized water reactor (PWR) nuclear fuel. The test facility has operated at the Product Engineering Development Laboratory, which … [Read more...]
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