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Reactor Thermal Hydraulics
Zaki, G. M., M. M. Farahat, and M. S. El-Genk, "MAGI Computer Code for Steady State Thermal Analysis of Boiling Water Power Reactors," Proc. Iraqi First Conference on Uses of Atomic Energy, Baghdad, April 1975. (Proceedings Article)
Zaki, G. M., M. M. Farahat, and M. S. El-Genk, "Mathematical Model for Boiling Water Reactors," Fifth All-Union Heat and Mass Transfer Conference, Minske, USSR, 1976. (proceedings).
Zaki , G.M., M.S. El-Genk, T.E. Williams, and J.S. Philbin, "Experimental Heat Transfer Studies for Water in an Annulus at Low Reynolds Number," Fundamentals of Forced Convections, Eds. F.A. Kulacki and R.D. Boyd, 42, ASME, NY, 113-120, 1985. (Refereed Article)
El-Genk, M. S., J. S. Philbin, and F.C. Foushee, "A Research Program Investigating Heat Transfer and Fluid Flow at Low Pressure," Proc. 10th TRIGA Owner-User Conference, College Station, TX, 6-9 April 1986. (Proceedings Article)
Zaki , G. M., M. S. El-Genk, and J. S. Philbin, "Natural Convection Heat Transfer with Application to the Annular Core Research Reactor (ACRR)," SAND85-2073, Sandia National Labs., Final Report (1986). (Technical Report)
El-Genk, M.S., G.M. Zaki, T.E. Williams, and J.S. Philbin, "Experimental Heat Transfer Studies of Laminar and Transition Flows of Water in a Vertical Annulus," J. International Communications in Heat an Mass Transfer, 13 No. 1, 67-75, 1986. (Refereed Article)
El-Genk, M. S., S. J. Haynes, and Sung-Ho Kim, "Experimental Studies for Critical Heat Flux at Low Flow of Water in Vertical Annuli Near Atmospheric Pressure," Report No. NE-125 (87), SNL-417-1 (November 1987). (Technical Report)
El-Genk, M. S. and D. V. Rao, "Heat Transfer Experiments of Unstable, Buoyancy Assisted and Opposed Laminar Flows in a Vertical Annulus", Report No. NE-123 (87), SNL-417-1 (November 1987). (Technical Report)
El-Genk, M.S., S.-H. Kim, G.M. Zaki, J.S. Philbin, J.F. Schulze, and F.C. Foushee, "Experimental Studies of the Air Coolability of TRIGA Reactors Following a Loss-of-Coolant Accident," J. Nuclear Technology, 76, 360-369, 1987.
Kim, Sung-Ho, M. S. El-Genk, R. R. Rubio, J. W. Brayson, and F. C. Foushee, "Heat Transfer Experiments and Correlation for Natural and Forced Circulation of Water in Rod Bundles," Proc. 11th TRIGA Owner-User Conference, Bethesda, MD, 10-13 April 1988. (Proceedings Article)
Rao, D.V., M.S. El-Genk, R.A. Rubio, J.W. Bryson, and F.C. Foushee, "Thermal Hydraulics Model for Sandia's Annular Core Research Reactor," Proc. 11th TRIGA Owner/User Conf., Washington, D.C., Apr. 9-13, 1988.
El-Genk, M. S., S. J. Haynes, and Sung-Ho Kim. "Critical Heat Flux Experiments for Low Flow of Water in Vertical Annuli Near Atmospheric Pressure," Particulate Phenomena and Multi-Phase Transport, (Ed., T. V. Veziroglu), Hemisphere Publishing Corp., 2, 1988, 377-402. (Proceedings Article)
El-Genk, M. S. and V. R. Dasari, "Observed Flow Instabilities and Measured Nusselt Numbers for Buoyancy Assisted and Opposed Laminar Flow in a Vertical Annulus," Particulate Phenomena and Multi-Phase Transport, (Ed., T. V. Veziroglu), Hemisphere Publishing Corp., 3, 1988, 107-120. (Proceedings Article)
El-Genk, M.S., Sung-Ho Kim, G.M. Zaki, M.Aker, and F. Foushee, "Experimental Heat Transfer Study of Free Convection of Atmospheric Air in Vertical Open Annuli at High Surface Temperatures," J. Chem. Eng. Comm., 63, 1988, 225-243. (Similar to Convective Heat Transfer Reference) "El-Genk, M.S., S.-H. Kim, and G.M. Zaki, "Free Convection Experiments of Atmospheric Air in Vertical Open Annuli," Chem. Eng. Comm., 63, 225-243, 1988
Rao , D. V. and M. S. El-Genk, "Critical Heat Flux Predictions for the Upgrade of Sandia's Annular Core Research Reactor," Final Report No. ISNPS - 312631-1-90, Institute for Space Nuclear Power Studies, University of New Mexico, Albuquerque, NM 87131 (February 1990). (Technical Report)
El-Genk, M.S. and D. Rao, "Critical Heat Flux Prediction for the Annular Core Research Reactor," Proc. Int. Topical Meeting on Safety of Noncommercial Nuclear Reactor Research and Irridiation Facilities, Boise, ID, Sept. 30-Oct. 4, 1990.
El-Genk, M.S. and D.V. Rao, "Thermal Hydraulics Model for the Annular Core Research Reactor," Proc. Int. Topical Meeting on Safety of Noncommercial Nuclear Reactor Research and Irridiation Facilities, Boise, ID, Sept. 30-Oct. 4, 1990.
El-Genk, M.S., J.Y. Yang, and N.J. Morley, "Thermal-Hydraulic Analysis of Pellet Bed Reactor," AIAA/NASA/OAI Conference on Advanced Space Exploration Initiative (SEI) Technologies, Cleveland, OH, Sept. 4-6, 1991.
El-Genk, M.S. and H. Xue, "An Investigation of Natural Circulation Decay Heat Removal from an SP-100 Reactor System for a Lunar Outpost," Proc. 9th Symposium on Space Nuclear Power Systems, AIP No.246(1), Albuquerque, NM, Jan. 12-16, 1992, 787-795.
El-Genk, M.S. and H. Xue, "Decay Heat Removal by Natural Circulation in a 500-kWe SP-100 Power System for a Lunar Outpost," J. Nuclear Technology, 100, 271-286, 1992.
Harper, F. T., E. D. Gorham, and M. S. El-Genk, "Simulation of Liquid Drop Breakup Behavior in a Flow Field Using Discrete Element Techniques," 5th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Salt Lake City, UT, 21-24 September 1992. (Refereed Article)
El-Genk, M.S. and H. Xue, "Natural Circulation Decay Heat Removal from an SP-100 Reactor System for a Lunar Outpost," Topics in Heat Transfer, (Eds. R.S. Downing, et al.), HTD-206-3(3), ASME, NY, 56-61, 1992.
Morley, N.J. and M.S. El-Genk, "Preliminary Thermal-Hydraulic Analysis of the Pellet Bed Reactor for Nuclear Thermal Propulsion," Proc. 6th Int. Top. Mtg. On Nuclear Reactor Thermal Hydraulics, Grenoble, France, Oct. 5-8, 1993, 835-842.
Morley, N.J. and M.S. El-Genk, "Thermal-Hydraulics Sensitivity Analysis of the Pellet Bed Reactor for Nuclear Thermal Propulsion," Proc. 11th Symposium on Space Nuclear Power and Propulsion, AIP No.301(3), Albuquerque, NM, Jan. 9-13, 1994, 773-781.
Morley, N. J. and M. S. El-Genk, "Two-Dimensional Thermal-Hydraulic Analyses of High Temperature Packed Beds, with Applications to the Pellet Bed Reactor," Final Report No. UNM-ISNPS -2-94, Institute for Space and Nuclear Power Studies, University of New Mexico, Albuquerque, NM 87131 (February 1994). (Technical Report)
Morley, N.J. and M.S. El-Genk, "Thermal-Hydraulic Analysis of the Pellet Bed Reactor for Nuclear Thermal Propulsion," J. Nuclear Engineering and Design, 149, 387-400, 1994.
Morley, N.J. and M.S. El-Genk, "Neutronics and Thermal-Hydraulics Analyses of the Pellet Bed Reactor for Nuclear Thermal Propulsion," J. Nuclear Technology, 109, 87-107, 1995.
Tournier, J.-M. and M.S. El-Genk, "Reactor Lithium Heat Pipes for HP-STMCs Space Reactor Power System," Proc. Space Technology and Applications International Forum (STAIF-2004), AIP No. 699, Albuquerque, NM, February 8-11, 2004, 781-792.
King. J. C. and M. S. El-Genk, “Solid-Core, Gas-Cooled Reactor for Space and Surface Power,” Proceedings of Space Technology and Applications International Forum (STAIF-06), AIP Conference Proceedings No. 813, American Institute of Physics, Melville, NY, 2006, 298 – 307.
King, J. C. and M. S. El-Genk, “Thermal-Hydraulic Analyses of the Submersion-Subcritical Safe Space (S^4) Reactor,” Proceedings of Space Technology and Applications International Forum (STAIF-07), AIP Conference Proceedings No. 880, American Institute of Physics, Melville, NY, 2007, 261 – 270.
El-Genk, M. S., “Space Nuclear Reactor Concepts for Avoidance of a Single Point Failure,” Proceedings 13th International Conference on Emerging Nuclear Energy Systems, Sumer Sahin, Editor, Istanbul, Turkey, 3 – 8 June, 2007.
Rodriquez, S. B., D. Louie, R. O. Gauntt, F. Gelbard, P. Pickard, R. Cole, K. McFadden, T. Drennen, B. Martin, L. Archuleta, S. Ravankar, K. Vierow, D., M. S. El-Genk, and J.-M. Tournier, “MELCOR-H2 Benchmarking of the SNL Transient Sulfuric Acid Decomposition Experiments,” Proceedings AICHE Spring Meeting, Houston, Texas, 22 – 27 April, 2006.
El-Genk, M. S., “Space Nuclear Reactor Power System Concepts with Static and Dynamic Energy Conversion,” J. Energy Conversion and Management Special Issue on Space Nuclear Power and Propulsion, 49 (3), 2008, 402 – 411.
Rodriguez, S. B. and M. S. El-Genk, “ Using Helicoides to Eliminate ‘Hot Streaking’ in the VHTR Lower Plenum,” Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 08), American Nuclear Society, Paper # 8079, Anaheim, CA, USA, 8-12 June 2008.
El-Genk, M. S., “Space Reactor Power Systems with No Single Point Failures,” J. Nuclear Engineering and Design (in print April, 2007).
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