61 |
Cross-channel transfer of linear momentumCruff, Russell William 12 1900 (has links)
No description available.
|
62 |
Time sampling error analysis and stochastic modeling of low-flowsAlhadeff, Samuel Jack 08 1900 (has links)
No description available.
|
63 |
An investigation of the small undular surge in a horizontal channel of circular cross sectionAdams, James Franklin 08 1900 (has links)
No description available.
|
64 |
A laboratory investigation of a rock riprap control structure in an open channelDavis, Gary Stanley 08 1900 (has links)
No description available.
|
65 |
An investigation of the sediment entrainment mechanismDangar, James Ivan 12 1900 (has links)
No description available.
|
66 |
Localized scour around a vertical circular pile in oscillatory flowAltinbilek, Hilmi Dogan 12 1900 (has links)
No description available.
|
67 |
A steady state thermal hydraulic analysis method for prismatic gas reactorsHuning, Alexander 27 August 2014 (has links)
A new methodology for the accurate and efficient determination of steady state thermal hydraulic parameters for prismatic high temperature gas reactors is developed. Two conceptual reactor designs under investigation by the nuclear industry include the General Atomics GT-MHR and the Department of Energy MHTGR-350. Both reactors use the same hexagonal prismatic block, TRISO fuel compact, and circular coolant channel array design.
Steady state temperature, pressure, and mass flow distributions are determined for the base reference designs and also for a range of values of the important parameters. Core temperature distributions are obtained with reduced computational cost over more highly detailed computational fluid dynamics codes by using efficient, correlations and first-principles-based approaches for the relevant thermal fluid and thermal transport phenomena. Full core 3-D heat conduction calculations are performed at the individual fuel pin and lattice assembly block levels. The fuel compact is treated as a homogeneous medium with heat generation. A simplified 1-D fluid model is developed to predict convective heat removal rates from solid core nodes. Downstream fluid properties are determined by performing a channel energy balance down the axial node length. Channel exit pressures are then compared and inlet mass flows are adjusted until a uniform outlet pressure is reached. Bypass gaps between assembly blocks as well as coolant channels are modeled. Finite volume discretization of energy, and momentum conservation equations are then formed and explicitly integrated in time. Iterations are performed until all local core temperatures stabilize and global convective heat removal matches heat generation.
Several important observations were made based on the steady state analyses for the MHTGR and GT-MHR. Slight temperature variation in the radial direction was observed for uniform radial powers. Bottom-peaked axial power distributions had slightly higher peak temperatures but lower core average temperatures compared to top and center-peaked power distributions. The same trend appeared for large bypass gap sizes cases compared to smaller gap widths. For all cases, peak temperatures were below expected normal operational limits for TRISO fuels. Bypass gap flow for a 3 mm gap width was predicted to be between 10 and 11% for both reactor designs. Single assembly hydrodynamic and temperature results compared favorably with those available in the literature for similar prismatic HTGR thermal hydraulic, computational fluid dynamics analyses.
The method developed here enables detailed local and core wide thermal analysis with minimal computational effort, enabling advanced coupled analyses of high temperature reactors with thermal feedback. The steady state numerical scheme also offers a potential for select transient scenario modeling and a wide variety of design optimization studies.
|
68 |
Water intake at the atmosphere-earth interface in a fractured rock system near Patagonia, ArizonaKilbury, Richard Kenneth. January 1984 (has links) (PDF)
Thesis (M.S. - Hydrology)--University of Arizona, 1984. / Includes bibliographical references (leaves 122-123).
|
69 |
Analysis and predictions of extreme coastal water levelsXu, Sudong. January 1900 (has links)
Thesis (Ph. D.)--Florida State University, 2007. / Advisor: Wenrui Huang, Florida State University, College of Engineering, Dept. of Civil and Environmental Engineering. Includes bibliographical references.
|
70 |
Numerical simulation of flow through a spillway and diversion structureGacek, Julian D. January 1900 (has links)
Thesis (M.Eng.). / Written for the Dept. of Civil Engineering and Applied Mechanics. Title from title page of PDF (viewed 2008/01/14). Includes bibliographical references.
|
Page generated in 0.0151 seconds