Latest Publications

Schriener, T.M., M.S. El-Genk, Armored Lightweight Heat Rejection Radiator for Lunar Surface Nuclear Reactor Power Systems. Proceedings ANS 2024 Nuclear and Emerging technologies for Space (NETS 2024), 2024.
El-Genk, M.S, T.M. Schriener, R. Altamimi, A. Hahn, Pumping Options for Versatile Test Reactor Molten Lead In-pile Test Cartridge. J. Nuclear Science and Engineering, 2023. 197 3082-3109
Altamimi, R., M.S. El-Genk, Equivalent Circuit Model for Predicting the Performance Characteristics of Direct Current-Electromagnetic Pumps. J Material Sciences and Engineering, 2023. 12(1) 629
Altamimi, R., M.S. El-Genk, Miniature DC Electromagnetic Pumps of Molten Lead and Sodium to Support Development of Gen-IV Nuclear Reactors. J Nuclear Engineering and Design, 2023. 410 112376
Altamimi, R., M.S. El-Genk, Magnetohydrodynamic Analyses of a Miniature Dual-Stages Electromagnetic Pump for Lead and Sodium In-pile Test Loops. J. Nuclear Science and Engineering, 2023. 1-27
Altamimi, R., M.S. El-Genk, Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors. J Nuclear Engineering and Design, 2023. 1-25
El-Genk, M.S., T. Schriener, Cybersecurity Analyses of a Space Reactor Power System under Simulated False Data Injection Attacks. Proceedings AIAA ASCEND Conference, 2023.
El-Genk, M.S., T. Schriener, Design and Analyses of Lightweight Radiator Module for Nuclear Reactor Lunar Surface Power. Proceedings AIAA ASCEND Conference, 2023.
El-Genk, M.S., T.M. Schriener, A.S. Hahn, Design Optimization and CFD and Performance Analyses of Miniature Axial-Centrifugal Flow Pumps for Circulating Molten Lead. J. Material Sciences & Engineering, 2022. 11:04 1-14
Schriener, T.M., M.S. El-Genk, Gas-lift enhanced natural circulation of alkali and heavy liquid metals for passive cooling of nuclear reactors. International Journal of Multiphase Flow, 2022. 143 103783

Recent Events

8/15/2023
Graduate Research Assistantships Available Fall 2023 at UNM-ISNPS
7/28/2023
Doctoral Graduation - Ragai Altamimi
1/17/2023
UNM, Purdue work to develop autonomous control architecture for microreactors
11/25/2022
First Year Progress Report for NASA Advanced Radiator Project

Contact

Physical Location:
Ferris Engineering Center
Room 1120

Mailing Address:
Institute for Space & Nuclear Power Studies
MSC01-1120
1 University of New Mexico
Albuquerque, NM 87131

Phone: 505.277.5442
Fax: 505.277.5433

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Publications By Topic : Very High Temperature Reactor (vhtr) Plants

Showing 63 results

El-Genk, M. S. and J.-M. Tournier, "Passive and Safe Thermal Coupling of Generation-IV VHTR to Hydrogen Fuel Production Complex". Proceedings Int. Conference on Advances in Energy Systems and Environmental Engineering (ASEE17), 2017.
El-Genk, M. S. and J.-M. Tournier, "Reliable and Safe Thermal Coupling of Generation-IV VHTR to a Hydrogen Fuel Production Complex". J. Thermal Science and Engineering Progress, 2017.
El-Genk, M. S. and J.-M. Tournier, "A Point Kinetics Model and Dynamic Simulation of Next Generation Nuclear Reactor". J. Progress in Nuclear Energy, 92, 91-103, 2016.
El-Genk, M.S., J.-M. Tournier, and C. I. Contescu, "Chemical Kinetics Parameters and Model Validation for the Gasification of PCEA Nuclear Graphite". Journal of Nuclear Materials, 444(1), 112-128, 2014.
El-Genk, M. S. and J. -M. Tournier, "Advances in Gasification of Nuclear Graphite: Chemical-Reactions Kinetics Model Validation and Analyses Results". In Graphite, Properties, Occurrences and Uses Book, Ch-1, 24838, 2013.
El-Genk, M. S. and J. -M. P. Tournier, "Chemical Kinetics Parameters of Nuclear Graphite Gasification". J. Nuclear Energy Science and Technology, 7(3), 258-284, 2013.
El-Genk, M. S., C. I. Contescu and J. -M. Tournier, "Gasfication of PCEA Graphite: Experiments, Chemical Kinetics, and Model Validation". In Proceedings of 14th International Nuclear Graphite Specialist Meeting (INGSM14), 2013.
Boyce, W. T. and M. S. El-Genk, "Numerical Simulation and Turbulent Convection Heat Transfer Correlation for Coolant Channels in a Very-High-Temperature Reactor". J. Heat Transfer Engineering, 34(1), 1-14., 2013.
El-Genk, M. S., "Recent Advances on Gasification of Nuclear Graphite: A Chemical Reactions Kinetics Approach". In Proceedings of 14th International Nuclear Graphite Specialist Meeting (INGSM14), 2013.
El-Genk, M. S. and J.-M. P. Tournier, "Sherwood Number Correlation for Nuclear Graphite Gasification at high Temperatures". J. Progress in Nuclear Energy, 62, 26-36, 2013.
Boyce, W. T. and M. S. El-Genk, "Thermal-Hydraulics Analyses of 1/6 Prismatic VHTR Core and Fuel Element with and without Bypass Flow". J. Energy Conversion and Management, 67, 326-341, 2013.
El-Genk, M. S. and J. -M. P. Tournier, "Transient Gasification in an NBG-18 Coolant Channel of a VHTR Prismatic Fuel Element". J. Progress in Nuclear Energy, 64, 16-30, 2013.
Travis, B. W. and M. S. El-Genk, "An Effective Thermal-Hydraulics Methodology for Prismatic Core HTGR and VHTR". Proceedings of 12th International Congress on Advances in Nuclear Power Plants (ICAPP�12), paper No. 12061, 24-28, 2012.
El-Genk, M. S and J.-M. P. Tournier, "Comparison of Gasification Kinetics Parameters of Different Types of Nuclear Graphite". Proceedings of 12th International Congress on Advances in Nuclear Power Plants (ICAPP�12), paper No. 12023, 24-28, 2012.
El-Genk, M. S. and J.-M. P. Tournier, "Comparison of Oxidation Model Predictions with Gasification Data of IG-110, IG-430 and NBG-25 Nuclear Graphite". J. Nuclear Materials, 420, 141-158, 2012.
El-Genk, M. S. and J.-M. P. Tournier, "Diffusion Velocity Correlation for Nuclear Graphite Gasification at High Temperatures and Low Reynolds Numbers". Proceedings of 12th International Congress on Advances in Nuclear Power Plants (ICAPP�12), paper No. 12022, 24-28, 2012.
El-Genk, M. S., J-M. P. Tournier and B. W. Travis, "Graphite Oxidation Simulation in HTR Accident Conditions �Final and 3rd Year Technical Report". Technical Report No. UNM-ISNPS-1-2012, Institute for Space and Nuclear Power Stud, 2012.
Rodriguez, S.B., F. A. Espinoza, S.L. Steinberg and M. S. El-Genk, "Towards a Unified Swirl Vortex Model". 42nd AIAA Fluid Dynamics Conference and Exhibit, Paper # AIAA-06112012, 25 � 28, 2012.
El-Genk, M. S. and J.-M. P. Tournier, "Validation of an Oxidation Model for NBG-18 Nuclear Graphite". J. Nuclear Engineering and Design, 250, 142-155, 2012.
El-Genk, M.S. and J. M. Tournier, "Comparison of Oxidation Model with Gasification data of IG-110, IG-430, and NBG-25 Nuclear Graphite, and Numerical Simulation of Turbulent Convection Heat Transfer in Coolant Channels ". ISNPS Report No. 1-2011, 2011.
Rodriguez, S. B. and M. S. El-Genk, "Coupled Computational Fluid Dynamics and Heat Transfer Analysis of VHTR Lower Plenum". Proceedings 11th International Congress on Advances in Nuclear Power Plants (ICAPP-2011), Paper # 11247, 2011.
M. S. El-Genk and Jean-Michel P. Tournier, "Development and Validation of a Model for the Chemical Kinetics of Graphite Oxidation". J. Nuclear Materials, 411, 193-207, 2011.
Rodriguez, S. B. and El-Genk, M. S., "Cooling of an Isothermal plate using a Triangular Array of Swirling Air Jets". Proceedings 14th International Heat Transfer Conference, Paper# IHTC14-22170, 2010.
El-Genk, M. S., Tournier, J.-M., P., and Gallo, B. M., "Dynamic Simulation of a Space Reactor System with Closed Brayton Cycle Loops". J. Propulsion and Power, 26(3), 394-406, 2010.
El-Genk, M. S. and Tournier, J.-M., "Effects of Working Fluid and Shaft Rotation Speed on the Performance of HTR Plants and the Size of CBC Turbo-Machine". J. Nuclear Eng. & Design, 239, 1811-1827, 2010.
Rodriguez, S. B., S. Domino and M. S. El-Genk, "Fluid Flow and heat Transfer Analysis of the VHTR Lower Plenum Using the FUEGO CFD Code". Proceedings CFD for Nuclear Reactor Safety (CFD4NRS-3), 2010.
El-Genk, M. S. and J.-M. Tournier, "Graphite Oxidation Simulation in HTR Accident Conditions: Development of a Graphite Oxidation Kinetics Model". Technical Report No. UNM-ISNPS-1-2010, University of New Mexico, 2010.
El-Genk. M. S. and Gallo, B. M., "High-Power Brayton Rotating Unit for Space Reactor and Solar Power System". J. Propulsion and Power, 26, 167-176, 2010.
Rodriguez, S. B., and El-Genk, M. S., "Numerical Investigation of Potential Elimination of hot streaking and stratification in the VHTR lower plenum using helicoid inserts". J. Nuclear Engineering and Design, 240, 995-1004, 2010.
Rodriguez, S. B. and El-Genk, M. S., "On enhancing VHTR Lower Plenum Heat Transfer and Mixing via Swirling Jets". Proceedings 10th International Congress on Advances in Nuclear Power Plants (ICAPP, Paper # 10160, 2010.
El-Genk, M. S. and Tournier, J.-M., "On Modes and Kinetics of Nuclear Graphite Oxidation in Massive Air or Steam Ingress". Proceedings 10th International Congress on Advances in Nuclear Power Plants (ICAPP, Paper # 10159, 2010.
El-Genk, M. S., and Tournier, J.-M., "On the Performance of Very High Temperature Reactor Plants with Direct and Indirect Closed Brayton Cycles". ASME J. Engineering for Gas Turbines and Power, 132, 032902-1 - 032902-7, 2010.
Tournier, J.-M., and M. S. El-Genk, "Axial Flow, Multi-Stage Turbine and Compressor Models". J. Energy Conversion and Management, 51, 16-29, 2009.
Gallo. B. M, and M.S. El-Genk, "Brayton Rotating Units for Space Reactor Power Systems". J. Energy Conversion and Management, 50(9), 2210-2232, 2009.
El-Genk, M. S. and Tournier, P. J.-M., "On the Performance of VHTR Plants with Direct and Indirect Closed Brayton Cycles". ASME J. Engineering of Gas Turbine and Power, 132, 032902-1 - 032902-7, 2009.
El-Genk, M. S. and Jean-Michel Tournier, "Performance Analyses of VHTR Plants with Direct and Indirect Closed Brayton Cycles". J. Progress in Nuclear Energy, 51, 526-542, 2009.
El-Genk, M. S. and Tournier, J.-M., "Small Size Turbo-Machines for HTR Plants". Proceedings ASME Power Conference (Power2009), Paper # POWER2009-81171, 2009.
Rodriguez, S. B, D. Louie, F. Gelbard, M. S. El-Genk, R. O. Gauntt, J.-M. Tournier, R. Cole, F. Gelbrad, K. McFadden, S. T. Revankar, and K. Vierow, T. Drennen, B. Martin, F. Espinoza, and L. Archuleta, "Transient Analysis of Sulfur-Iodine Cycle Experiments and Very High Temperature Reactor Simulations using MELCOR-H2". J. Nuclear Technology, 166, 76-85, 2009.
Tournier, J.-M. and M. S. El-Genk, "Alternative Working Fluids to Reduce Size of Turbomachinery for VHTR Plants". Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 08), American Nuclear Society, Paper # 8072, 2008.
El-Genk, M. S., J.-M. Tournier, "Noble Gas Binary Mixtures for Gas-Cooled Reactor Power Plants". J. Nuclear Engineering and Design, 238(6), 1353-1372, 2008.
Rodriguez, S. B. and M.S. El-Genk, "On Eliminating 'Hot Streaking' and Stratifcation in the VHTR Lower Plenum Using Helicoid Inserts". Proc. High Temperature Reactor Conference (HTR2008), Paper # HTR2008-58292, 2008.
Mohamed S. El-Genk and J.M. Tournier, "On the Use of Noble Gases and Binary Mixtures as Reactor Coolants and CBC Working Fluids". J. Energy Conversion and Management, 49(7), 1882-1891, 2008.
Tournier, J.-M., and M. S. El-Genk, "Properties of Helium, Nitrogen, and He-N2 Binary Gas Mixtures". J. Thermophysics and Heat Transfer, 22(3), 442-456, 2008.
Tournier, J.-M., and M. S. El-Genk, "Properties of Noble Gases and Binary Mixtures for Closed Brayton Cycle Applications". J. Energy Conversion and Management Special Issue on Space Nuclear Power and Propulsion, 49(3), 469-492, 2008.
Tournier, J.-M., and M. S. El-Genk, "Transport Properties of He-N2 Binary Mixtures for CBC Space Applications". Proceedings of Space Technology and Applications International Forum (STAIF-08), AIP Conference Proceedings No.969, 637-647, 2008.
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, 2008.
El-Genk, M.S. and Tournier, J.M, "Gas-Cooled reactor point kinetics Model for MELCOR-H2". ISNPS Report NO 1-2007, 2007.
El-Genk, M. S., and Jean-Michel Tournier, "Noble Gas Binary Mixtures for CBC Space Reactor Power Systems". J. Propulsion and Power, 23(4), 863-873, 2007.
El-Genk, M. S., and J.-M. Tournier, "Noble Gas, Binary Mixtures for Commercial Gas-Cooled Reactor Systems". Proceedings 13th International Conference on Emerging Nuclear Energy Systems, 2007.
Tournier, J.-M., M. S. El-Genk, and B. Gallo, "Best Estimates of Binary Mixtures Properties for Closed Brayton Cycle Space Applications". Proceedings of International Energy Conversion Engineering Conference, IECEC-2006, Paper No. AAIA-2006-4154, 2006.
Rodriquez, S. B., D. Louie, R. O. Gauntt, F. Gelbard, P. Pickard, R. Cole, K. McFadden, T. Drennen, B., "MELCOR-H2 Benchmarking of the SNL Transient Sulfuric Acid Decomposition Experiments". Proceedings AICHE Spring Meeting, 2006.
Tournier, J. -M., and M.S. El-Genk, "Models of Turbine and Compressor Units for MELCOR Secondary System Modules". ISNPS 2-2006, 2006.
El-Genk, M.S., and Jean-Michel Tournier, "Noble Gases Binary Mixtures for Brayton Commercial Nuclear Power Plants". Trans. Am. Nucl. Soc., 95, 915-916, 2006.
El-Genk, M. S. and J.-M. Tournier, "Selection of Noble Gas Binary Mixtures for Brayton Space Reactor Power Systems". Proceedings of International Energy Conversion Engineering Conference, IECEC-2006, Paper No. AAIA-2006-4168, 2006.
El-Genk, M.S. and Tournier, J.M, "Thermo-Chemical Generation of Hydrogen using high Temperature Gas-cooled power cycle modeling recommendation in MELCOR". ISNPS Report NO 3-2006, 2006.
El-Genk, M.S., "High-Energy-Utilization, Dual-Mode System Concept for Mars Missions". J. Propulsion and Power, 17(2), 340-346, 2001.
Liscum-Powell, J. and M.S. El-Genk, "Design and Optimization of the Pellet Bed Reactor for Bimodal Space Power and Propulsion Applications". Final Report No. UNM-ISNPS 2-95, 1995.
Pelaccio, D.G., M.S. El-Genk, and D.P. Butt, "Hydrogen Corrosion Considerations of Carbide Fuels for Nuclear Thermal Propulsion Applications". J. Propulsion and Power, 11(6), 1338-1348, 1995.
El-Genk, M.S., N.J. Morley, D.G. Pelaccio, A. Juhasz, "Pellet Bed Reactor Concepts for Nuclear Propulsion Applications". J. Propulsion and Power, 10(6), 817-827, 1994.
Morley, N.J. and M.S. El-Genk, "Manned Mars Rover Powered by a Nuclear Reactor: Radiation Shield Analysis". J. Nuclear Technology, 99, 188-202, 1992.
Morley, N.J. and M.S. El-Genk, "Passive Decay Heat Removal in the PeBR Concept for Nuclear Thermal Propulsion". Proc. 9th Symposium on Space Nuclear Power Systems, AIP No.246(3), 955-966, 1992.
Dobranich, D. and M.S. El-Genk, "Heat Transfer and Thermal Stress Analysis of Multi-Layered Fuel Particles". Proc. 7th Symposium on Space Nuclear Power Systems, 2, 1026-1032, 1990.
Buden , D., M. S. El-Genk, A. Parlos, J. Mims, J. McGhee, and S. Lapin, "Pellet Bed Reactor Concept". Final Report, U.S. DOE San Francisco Operation, Contract No. DE-AC03-86SF16508, 1987.

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