William D. Pointer, Ph.D.

Affiliations: 
2001 The University of Tennessee, Knoxville, TN, United States 
Area:
Nuclear Engineering, Mechanical Engineering
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"William Pointer"

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Arthur Ruggles grad student 2001 University of Tennessee
 (Experimental characterization of flow patterns and flow stability in the bulk mercury flow field of the Spallation Neutron Source mercury target.)
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Publications

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Merzari E, Fischer P, Pointer WD, et al. (2012) On the interaction of boundary layer and mixing layer in stratified pipe flow American Society of Mechanical Engineers, Fluids Engineering Division (Publication) Fedsm. 1: 767-773
Merzari E, Fischer P, Pointer WD. (2012) Optimal disturbances in three-dimensional natural convection flows American Society of Mechanical Engineers, Fluids Engineering Division (Publication) Fedsm. 1: 921-928
Merzari E, Pointer WD, Smith JG, et al. (2012) Numerical simulation of the flow in wire-wrapped pin bundles: Effect of pin-wire contact modeling Nuclear Engineering and Design. 253: 374-386
Lomperski S, Merzari E, Obabko A, et al. (2012) The MAX facility for CFD code validation International Congress On Advances in Nuclear Power Plants 2012, Icapp 2012. 3: 1873-1879
Tentner A, Pointer WD, Lo S, et al. (2009) Development and validation of a computational fluid dynamics model for the simulation of two-phase flow phenomena in a boiling water reactor fuel assembly International Conference On Nuclear Engineering, Proceedings, Icone. 5: 275-284
Pointer WD, Tentner A, Sofu T, et al. (2008) Prediction of boiling water reactor assembly void distributions using a two-phase computational fluid dynamics model International Conference On Nuclear Engineering, Proceedings, Icone. 2: 321-329
Smith JG, Babin BR, Pointer WD, et al. (2008) Effects of mesh density and flow conditioning in simulating 7-f>in wire wrapped fuel pins International Conference On Nuclear Engineering, Proceedings, Icone. 2: 755-763
Tentrier A, Pointer WD, Sofu T, et al. (2008) Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies Societe Francaise D'Energie Nucleaire - International Congress On Advances in Nuclear Power Plants - Icapp 2007, "the Nuclear Renaissance At Work",. 5: 2682-2691
Pointer WD, Tentner A, Sofu T, et al. (2007) Eulerian two-phase computational fluid dynamics for boiling water reactor core analysis Joint International Topical Meeting On Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + Sna 2007
Pointer WD, Ruggles AE. (2003) An approach for selection of flow regime and models for conservative evaluation of a vessel integrity monitoring system for water-cooled vacuum vessels Nuclear Technology. 141: 202-210
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