Publications By Topic : Terrestrial Nuclear Power

• Kresl-Hotz, K.R., El-Genk, M.S., Schriener, T.M., "CFD Analyses of the Flow Mixing and Stratification in Pool Type SFR". Proceedings ANS Student Conference 2025, 2025.
• Kresl-Hotz, K.R., El-Genk, M.S., Schriener, T.M., "Numerical Mesh Refinement for Flow Mixing in Pool Type SFR". Proceedings ANS Student Conference 2025, 2025.
• 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, 1-25, 2023.
• Altamimi, R., M.S. El-Genk, "Equivalent Circuit Model for Predicting the Performance Characteristics of Direct Current-Electromagnetic Pumps". J Material Sciences and Engineering, 12(1), 629, 2023.
• 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, 1-27, 2023.
• 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, 410, 112376, 2023.
• 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, 197, 3082-3109, 2023.
• El-Genk, M.S, T.M. Schriener, "A cybersecurity platform for simulating transient responses of emulated programmable logic controllers in instrumentation and control systems for a pwr plant". J. Cyber Security Technology, 6(1-2), 65-90, 2022.
• 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, 11:04, 1-14, 2022.
• 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, 143, 103783, 2022.
• El-Genk, M.S, T.M. Schriener, "Simulated false data injections attacks on emulated and hardware programmable logic controllers of the pressurizer in a representative pressurized water reactor plant". J. Cyber Security Technology, 6(4), 216-241, 2022.
• El Genk, M.S., T.M. Schriener, A. Hahn, C. Lamb, R. Fasano, C. Lamb, "LOBO Nuclear Reactor Power Plants CyberSecurity (LOBO NCS) Platform". Proceedings of the 12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021), 2021.
• El Genk, M.S., T.M. Schriener, L. Palomino, "Passive and Walk-Away Safe Small and Micro Reactors for Electricity Generation and Production of Process Heat for Industrial Uses". J. Nuclear Engineering and Radiation Science, 7, 031302 1-12, 2021.
• El Genk, M.S., R. Altamimi, T.M. Schriener, "Pressurizer Dynamic Model and Emulated Programmable Logic Controllers for Nuclear Power Plants Cybersecurity Investigations". Annals of Nuclear Energy, 154, 108121, 2021.
• Schriener, T.M. and M.S. El-Genk, "Response of Programmable Logic Controllers of the Pressurizer in a Representative PWR Plant Following a False Data Injection". Proceedings of the 12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021), 2021.
• Fasano, R., C. Lamb, M.S. El Genk, T.M. Schriener, A. Hahn, "Emulation methodology of programmable logic controllers for cybersecurity applications". Proceedings of the 2020 28th International Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference IC, 2020.
• El Genk, M.S., T.M. Schriener, R. Altamimi, A. Hahn, C. Lamb, R. Fasano, "NICSim: Nuclear Instrumentation & Control Simulation For Evaluating Response To Cyber Attacks". Proceedings of the 2020 28th International Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference IC, 2020.
• El-Genk, MS, Schriener, TM, Lamb, CC, "Nuclear Instrumentation and Control Simulation (NICSim) Platform for Investigating Cybersecurity Risks". In Trans. ANS 2020, 2020.
• Altamimi, R, El-Genk, MS, Schriener, TM, "Pressurizer Model and PLCs for Investigation of Cybersecurity of PWR Plants". In Trans. ANS 2020, 2020.
• Hahn, AS, El-Genk, MS, Schriener, TM, "Programmable Logic Controller of a Pressurized Water Reactor Core Protection Calculator". In Trans. ANS 2020, 2020.
• Hahn, A., T.M. Schriener, M.S. El Genk, "Selection and validation of fast and synchronous interface to the controller of a space nuclear reactor power system". Proceedings of the 2020 28th International Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference IC, 2020.
• Schriener, TM, El-Genk, MS, "Steam Generator Model and Controller for Cybersecurity Analyses of Digital I&C Systems in PWR Plants". In Trans. ANS 2020, 2020.
• El Genk, M.S., T.M. Schriener, L. Palomino, "Walk-Away Safe Modular Small and Micro Reactors for Electricity Generation and Process Heat". Proceedings of the 2020 28th International Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference IC, 2020.
• El-Genk, M. S., and L. M. Palomino, "A Walk-Away Safe, Very Small, Long-LIfe, Modular (VSLLIM) Reactor for portable and Stationary Power". Annals of Nuclear Energy, 129, 181-198, 2019.
• Palomino, L. M. and M.S. El-Genk, "CFD Analyses of Liquid Sodium Heat Transfer in 19-rod Hexagonal Bundles with Scalloped Walls". International J. Heat and Mass Transfer, 144, 118637, 2019.
• El-Genk, MS, "NICSim: Nuclear Instrumentation and Control Simulation for Evaluating Response to Cyber-attack". , 2019.
• Palomino, L. M., M. S. El-Genk, and T. M. Schriener, "Post-Operation Dose Rate Estimates for Very-Small, Long-LIfe, Modular (VSLLIM) Reactor". ASME Journal of Nuclear Engineering and Radiation Science, 115, 2019.
• Palomino, L. M. and M.S. El-Genk, "VSLLIM - Passive Decay Heat Removal by Natural Circulation of Ambient Air". J. Thermal Science and Engineering Progress, 11, 50-65, 2019.
• El-Genk, M. S. and T. M. Schriener, "Convection Heat Transfer of Alkali Liquid Metals and LBE in Hexagonal Bundles of Uniformly Heated Tubes with Helical Spacers". Thermal Science and Engineering Progress, 5, 339-350, 2018.
• El-Genk, M. S. and T. M. Schriener, "Post-Operation Radiological Source Term and Dose Estimates for the Scalable LIquid Metal-cooled small Modular Reactor". Annals of Nuclear Energy , 115, 442-458, 2018.
• Schriener, T. M., and M. S. El-Genk, "Transient and Safety Analyses of "SLIMM" - a Walkaway Safe Small Modular Reactor". Journal of Nuclear Energy Science and Power Generation, 7:3, 442-458, 2018.
• El-Genk, M. S. and T. M. Schriener, "A Review and Correlations for Convection Heat Transfer and Pressure Losses in Toroidal and Helically Coiled Tubes". J. Heat Transfer Engineering, 38(5), 2017.
• El-Genk, M. S. and T. M. Schriener, "A Review of Experimental Data and Heat Transfer Correlations for Parallel Flow of Alkali Liquid Metals and Lead-Bismuth Eutectic in Bundles". J. Nuclear Engineering and Design, 317, 2017.
• El-Genk, M. S., L. M. Palomino, and T. M. Schriener, "Low-Enrichment and Long-Life Scalable LIquid Metal Cooled Small Modular Reactor (SLIMM-1.2)". J. Nuclear Engineering and Design, 316, 163-185, 2017.
• Haskins, D. A. and M. S. El-Genk, "Natural Circulation Thermal-hydraulics Model and Analyses of "SLIMM"- A Small Modular Reactor". Annals of Nuclear Energy, 101, 516-527, 2017.
• 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., "A Fail Safe, Passive Operation Small Modular Nuclear Reactor for Electricity Generation and Process Heat Production". Proceedings AIChE Annual Meeting, 2016.
• 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.
• Haskins, D. A. and M. S. El-Genk, "CFD Analyses and Correlation of Pressure Losses on the Shell-Side of Concentric, Helically-Coiled Tubes Heat Exchanger". J. Nuclear Engineering and Design, 305, 531-546, 2016.
• Palomino, L. and M. S. El-Genk, "CFD and Thermal-Hydraulics Analyses of "SLIMM" Reactor Passive Decay Heat Removal by Natural Circulation of Ambient Air". J. Nuclear Technology, 195(1), 1-14, 2016.
• El-Genk, M. S., "Small Modular Nuclear Reactors: Potential, Challenges and Opportunities". Proceedings Energy Policy Research Institute Conference-EPRI 6th, 2016.
• Schriener, T. M. and M. S. El-Genk, "Convection Heat Transfer Analyses and Correlation for Alkali Liquid Metals in Uniformly Heated Tubes". Proceedings, 16th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-16), Paper# 13512, 2015.
• Schriener, T.M. and M.S. El-Genk, "Convection Heat Transfer of NaK-78 Liquid Metal in a Circular Tube and a Tri-lobe Channel". Int. J. Heat and Mass Transfer, 86, 234-243, 2015.
• Haskins, D. and M.S. El-Genk, "Natural Circulation Model and Performance Analyses of "SLIMM" - a Small, Modular Sodium-Cooled Reactor". Proceedings, 16th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-16), Paper# 13514, 2015.
• Palomino, L. and M. S. El-Genk, "SLIMM Decay Heat Removal by Natural Convection of Ambient Air". Proceedings, 16th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-16), Paper# 13513, 2015.
• El-Genk, M. S. and L. M. Palomino, "SLIMM-Scalable Liquid Metal Cooled Small Modular Reactor: Preliminary Design". Progress in Nuclear Energy, 85, 56-70, 2015.
• 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.
• Schriener, T.M. and M.S. El-Genk, "Comparative CFD Analyses of Liquid Metal Cooled Reactor for Lunar Surface Power". J. Nuclear Engineering and Design, 280, 105-121, 2014.
• El-Genk, M.S., and L. M. Palomino, "SLIMM-Neutronic Analyses and Lifetime Estimates". Proceedings International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Paper #14232, 1272-1280, 2014.
• El-Genk, M.S. and L. M. Palomino, "SLIMM-Scalable Liquid Metal Cooled Small Modular Reactor". Proceedings International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Paper #14076, 438-446, 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., 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.
• 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, "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, "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.
• 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.
• M. R. Taha and M. S. El-Genk, "An Investigation of Indigenous Ingredients in New Mexico for Nuclear Compliant Ultra High Performance Concrete (UHPC)". Proceedings 9th International Symposium on High Performance Concrete , 2011.
• 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.
• 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., "Nuclear Power in the Gulf Cooperation Council (GCC) States: Promise, Strategies and Challenges". Int. J. Nuclear Energy Science and Technology, 5(3), 248-274, 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.
• El-Genk, M. S., "Prospects for Nuclear Power in the Middle East and North Africa". Garten and Rothkopf Publications, 2010.
• El-Genk, M. S., "The Challenges of Introducing Nuclear Power in the Gulf Cooperation Council States". Int. J. Nuclear Governance, Economy and Ecology, 5(3), 248-274, 2010.
• 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., "On the Introduction of Nuclear Power in The Middle East Countries: Promise, Strategies, Vision, and Challenges". J. Energy Conversion and Management, 49(10), 2618-2628, 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., and M.S. El-Genk, "Performance Models and Results of Axial-Flow, Multistage Turbine and Compressor units and Generic Ehat Exchanger for CBC Nuclear Power Plants, and FORTRAN Source Codes for MELCOR-H2". ISNPS Report No. 3-2007, 2007.
• Rodriguez, S. B., R. O. Gauntt, R. Cole, K. McFadden, F. Gelbard, L. Malczynski, B. Martin, S. Ravankar, K. Vierow, D. Louie, L. Archuleta, M. S. El-Genk, and J.-M Tournier, "Addition of Secondary System Modules and a Graphical User Interface into MELCOR-H2 Phase 1". Trans. Am. Nucl. Soc. , 95, 917-920, 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.
• Rodriguez, S. B., R. O. Gauntt, R. Cole, K. McFadden, F. Gelbard, L. Malczynski, B. Martin, S. Ravankar, K. Vierow, D. Louie, L. Archuleta, M. S. El-Genk, and J.-M Tournier, "MELCOR-H2: A Modular, Generalized Tool for the Dynamic Simulation and Design of Fully-Coupled Nuclear Reactor/Hydrogen Production Plants". Trans. Am. Nucl. Soc. , 95, 889-890, 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 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. and J.-M. Tournier, "Review of Refractory Metal Alloys and Mechanically Alloyed-Oxide Dispersion Strengthened Steels for Space Nuclear Power Systems". J. Nuclear Materials, 340, 93-112, 2005.
• El-Genk, M.S. and J.-M. Tournier, "Mechanically Alloyed-Oxide Dispersion Strengthened Steels for Use in Space Nuclear Power Systems". Proceedings of Space Technology and Applications International Forum (STAIF-04), AIP No. 669, 829, 2004.
• El-Genk, M.S. and J.-M. Tournier, "Analyses of Static Energy Conversion Systems for Small Nuclear Power Plants". Progress in Nuclear Engineering, 42(3), 283-310, 2003.
• El-Genk, M. and Jean-Michel Tournier, "Nuclear Power Plant Concepts with Dynamic and Static Combined Energy Conversion". Proceedings of the International Congress on Advanced Nuclear Power Plants (ICAPP-03), 2003.
• El-Genk, M.S. and H.H. Saber, "An Investigation of the Breakup of an Evaporating Liquid Film, Falling Down a Vertical, Uniformly Heated Wall". J. Heat Transfer, 124, 39-50, 2002.
• El-Genk, M. S. and Jean-Michel Tournier, "Performance Analysis of BAPL Alkali- Metal Thermal-To-Electric Converter". Institute for Space and Nuclear Power Studies, ISNPS Report No. UNM-ISNPS-1-2002, 2002.
• El-Genk, M.S., and J.-M. Tournier, "Static Converter for High Energy Utilization, Modular, Small Nuclear Power Plants". Proc. ICONE-10, 2002.
• El-Genk, M. S. and Hamed H. Saber, "Breakup of an Evaporating Liquid Film falling Down a vertical heated Surface". Proc. 35rd National Heat Transfer Conference, NHTC01-116118, 2001.
• El-Genk, M.S. and H.H. Sabe, "Minimum Thickness of a Flowing Down Liquid Film on a Vertical Surface". Int. J. Heat and Mass Transfer, 44(15), 2809-2825, 2001.
• El-Genk, M. S., Jean-Michel Tournier, and Yoichi Momozaki, "Novel, Integrated Reactor/Power Conversion System (NIR/PCS): Design and Analysis of Alkali Metal Thermal-to-Electric Units and Interfacing with Nuclear Reactor". ISNPS Report No. UNM-ISNPS-2-2001, 2001.
• El-Genk, M.S. and J. -M. Tournier, "Numerical Modeling of High Temperature Heat Pipe Transients, Including Startup from a Frozen State". ISNPS Report 1-2001, 2001.
• Tournier, J.-M. and M.S. El-Genk, "User's Manual for H2PAC A Two-Dimensional High-Tempearture Heat Pipe Analysis Code, Including Startup from a Frozen State". ISNPS Report 1-2001, 2001.
• El-Genk, M.S. and H.H. Saber, "An Analysis of Depleted Uranium Dioxide Etching Experiments". J. Nuclear Technology, 132(2), 2000.
• Veilleux, J.M., M. El-Genk, E. Chamberlin, C. Munson, and J. Fitzpatrick, "Etching of U02 in NF3 RF Plasma Glow Discharge". J. Nuclear Materials, 277, 315-324, 2000.
• El-Genk, M. S, Jean-Michel Tournier, Jeffery King, and Yoichi Momozaki, "Novel Integrated Reactor/Power Conversion System (NIR/PCS): Alkali Metal Thermal-to-Electric Energy Conversion". Institute for Space and Nuclear Power Studies, ISNPS Report No. UNM-ISNPS-3-2000, 2000.
• Saber, H.H. , M.S. El-Genk, and J.M. Veilleux, "An Analysis and Modeling of the Etching Depleted Uranium Dioxide in NF3, RF Glow Discharge Plasma". Proc. WERC 1999 Conference on the Environment, 1999.
• Abdel-Fattah, A.I. and M.S. El-Genk, "An Experimental Investigation of Colloid Deposition on Solid Surfaces". Proc. WERC 1999 Conference on the Environment, 1999.
• El-Genk, M.S., H.H. Saber, and J. Veilleux, "Analysis and Modeling of Decontamination Experiments of Depleted Uranium Dioxide in RF Plasma". Annals of New York Academy of Sciences on 'Heat and Mass Transfer Under Plasma Conditions, 891, 174-182, 1999.
• Veilleux, J.M., M.S. El-Genk, H.H. Saber, E.P. Chamberlin, C. Munson, and J. FitzPatrick, "Chemical Species in RF Plasma Decontamination of Depleted Uranium Oxide". Proc. WERC 1999 Conference on the Environment, 1999.
• El-Genk, M.S. and C. Gao, "Experimental Investigation of Pool Boiling from a Downward-Facing Hemispherical Stainless-Steel Surface". J. Heat and Technology, 16, 65-75, 1999.
• El-Genk, M.S. and C. Gao, "Experiments on Pool Boiling of Water from Downward Facing Hemispheres". J. Nuclear Technology, 125, 52-69, 1999.
• Saber, H.H. and M.S. El-Genk, "Multi-Species Counter-Current Diffusion Model for Etching Depleted Uranium Oxide in NF3, RF Glow Discharge". Proc. 33rd National Heat Transfer Conf., 1999.
• Veilleux, J.M., M.S. El-Genk, E.P. Chamberlin, C. Munson, and J. Fitzpatrick, "Plasma Decontamination of Uranium Oxide from Stainless Steel Surfaces". Proc. WERC/WRHSRC/NMHWMS 98 Joint Conference on the Environment, 1999.
• Abdel-Fattah, A. I and M.S. El-genk, "Preliminary Investigation of Colloid Deposition in a Parallel-Plate Cell". Proc. Am. Chem. Soc 217th. National Mtg. on Interfacial and Colloidal Phenomina in Aquatic Environment, 1999.
• Hasan, A.A. and M.S. El-Genk, "An Investigation of the Interaction of Uranium with Silica Colloids in Batch and Column Experiments". Proc. WERC/WRHSRC/NMHWMS 98 Joint Conference on the Environment, 1998.
• El-Genk, M.S. and H. H. Saber, "Heat Transfer Correlations for Liquid Film in the Evaporator of Enclosed, Gravity-Assisted Thermosyphons". J. Heat Transfer, 120, 477-484, 1998.
• El-Genk, M.S. and H. Saber, "Heat Transfer Correlations for Small, Uniformly Heated Liquid Pools". Int. J. Heat and Mass Transfer, 41(2), 261-274, 1998.
• Gao, C. and M.S. El-Genk, "Nucleate Boiling on Downward-Facing Hemispherical Surfaces". Proc. 7th AIAA/AIChE Joint Thermophysics and Heat Transfer Conference, HTD-357(3), 55-62, 1998.
• El-Genk, M.S. and C. Gao, "Pool Boiling Heat Transfer from Downward-Facing Hemispherical Aluminum and Stainless-Steel Surface". Proc. 6th Int. Conf. on Nuclear Engineering, ICONE-6, 1998.
• El-Genk, M.S. and H. Saber, "Thermal Conductance of the Evaporator Section of Closed Two-Phase Thermosyphons (CTPT)". Proc. 7th AIAA/ASME Thermophysics and Heat Transfer Conference, HTD-357(3), 99-106, 1998.
• Roemer, G., M.S. El-Genk, and E. Nuttal, "A Colloid-Facilitated Transport Model and Its Application to Site Characterization". Proc. WERC/HSRC Joint Conference on the Environment, 1997.
• Tournier, J.-M. and M.S. El-Genk, "Analysis of a Lithium Fluoride, Porous Thermal Energy Storage Unit Subjected to Cyclical Thermal Loading". Proc. Space Technology and Applications International Forum (STAIF-97), AIP No.387(1), 397-413, 1997.
• El-Genk, M.S. and H. Saber, "Flooding Limit in Closed, Two-Phase Flow Thermosyphons". Int. J. Heat and Mass Transfer, 40(9), 2147-2164, 1997.
• Abdel-Fattah, A. and M.S. El-Genk, "Kinetics of Colloid Adsorption onto a Stagnant Air/Liquid Interface". Proc. WERC/HSRC Joint Conference on the Environment, 1997.
• El-Genk, M.S. and H.H. Saber, "Liquid Film Heat Transfer in the Evaporator of Two-Phase Thermosyphons". ASME Proc. 32nd National Heat Transfer Conf., HTD-349, 105-111, 1997.
• El-Genk, M.S. and H.H. Saber, "Liquid Pool Heat Transfer in Small, Cylindrical Enclosures with Uniform Wall Heating". AIChE Sym. Series-Heat Transfer, Proc. 10th Int. Heat Pipe Conference, 314(93), 131-137, 1997.
• El-Genk, M. S. and R. Busch, "New Mexico Opportunities in Nuclear Engineering (NMONE) Fellowship Program". Trans. Am. Nucl. Soc. , 91, 998-999, 1997.
• Veilleux, J.M., M.S. El-Genk, C. Munson, E.P. Chamberlin, and J. Fitzpatrick, "Plasma Decontamination of Uranium from the Interior of Aluminum Objects". Proc. WERC/HSRC Joint Conference on the Environment, 1997.
• El-Genk, M.S. and C. Gao, "Visualization of Pool Boiling on Downward-Facing Convex Surfaces". Proc. 5th Int. Topical Meeting on Nuclear Thermal-Hydraulics, Operation, and Safety (NUTHOS-5), 1997.
• Veilleux, J.M. and M.S. El-Genk, "Critical Issues in Applying Plasma Technology for Treating Hazardous, Radioactive, and Mixed Waste". 1996 AIChE Spring Annual Meeting, 1996.
• El-Genk, M.S. and H.H. Saber, "Effect of Dynamic Shear Stress on Thermosyphon Flooding Limit". AIChE Symp. Series-Heat Transfer, 301(92), 342-348, 1996.
• Gao, C. and M.S. El-Genk, "Effect of material properties and Surface Curvatures on Pool Boiling from Downward-Facing Convex Surfaces". Final Report UNM-ISNPS 1-1996, 1996.
• Veilleux, J.M. and M.S. El-Genk, "Plasma Technology for Treating Hazardous, Radioactive, and Mixed Waste: Critical Technology Issues and Preliminary Results". Proc. SPECTRUM 1996, 1996.
• Veilleux , J. M. and M. S. El-Genk, "Critical Issues in Plasma Technology Implementation for the Treatment of Hazardous, Radioactive, and Mixed Waste". Seventh National Technology Information Exchange (TIE) Workshop, 1995.
• El-Genk, M.S. and A.G. Glebov, "Effect of Subcooling and Wall Thickness on Pool Boiling from Downward-Facing Curved Surfaces in Water". Proc. 7th Int. Meeting on Nuclear Reactor Thermal-Hydraulics, NURETH-7, 1, NUREG/CP-0142, 353-376, 1995.
• El-Genk, M.S. and A.G. Glebov, "Effect of Subcooling on Film Boiling from a Downward-Facing Curved Surface in Water". AIChE Symp. Series-Heat Transfer, 306(91), 125-131, 1995.
• El-Genk, M.S. and A.G. Glebov, "Transient Pool Boiling from Downward-Facing Curved Surfaces". Int. J. Heat and Mass Transfer, 38(12), 2209-2224, 1995.
• Guo, Z. and M.S. El-Genk, "Liquid Microlayer Evaporation During Nucleate Boiling on the Surface of a Flat Composite Wall". Int. J. Heat and Mass Transfer, 37(11), 1641-1655, 1994.
• El-Genk, M.S., A.G. Glebov, and Z. Guo, "Pool Boiling from Downward-Facing Curved Surface in Saturated Water". Proc. 10th Int. Heat Transfer Conference, 5, 45-50, 1994.
• Guo, Z. and M.S. El-Genk, "Evaporation of a Liquid Microlayer on Uniformly Heated Flat Composite Surfaces". Heat Transfer on the Microscale-1993, HTD-253, 75-80, 1993.
• El-Genk, M.S., B. Su, and Z. Gu, "Experimental Studies of Forced, Combined and Natural Convection of Water in Vertical Nine-Rod Bundles with a Square Matrix". Int. J. Heat and Mass Transfer, 36(9), 2359-2374, 1993.
• Su, B., and M.S. El-Genk, "Forced Convection of Water in Rod-Bundles". Int. Comm. Heat Mass Transfer, 20, 295-300, 1993.
• El-Genk, M.S. and Z. Guo, "Transient Boiling from Inclined and Downward-Facing Surfaces in a Saturated Pool". Int. J. Refrig., 16(6), 414-422, 1993.
• El-Genk, M.S., B. Su, and Z. Guo, "Forced, Combined and Natural Convections of Water in a Vertical Nine Rod Bundle with a Square Lattice and P/D=1.5". Proc. 28th National Heat Transfer Conference, 1992.
• El-Genk, M.S., L. Huang, and Z. Guo, "Heat Transfer Between a Square Flat Plate and a Perpendicularly Impinging Circular Air Jet". Enhanced Heat Transfer, HT-202, 33-38, 1992.
• El-Genk, M.S. and Z. Guo, "Saturated and Subcooled Pool Boiling from Downward-Facing and Inclined Surfaces". Proc. Engineering Foundation Conference on Pool and External Flow Boiling, 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, 1992.
• El-Genk, M.S. and Z. Guo, "Transient Critical Heat Flux for Inclined and Downward-Facing Flat Surfaces". Proceedings of the 28th National Heat Transfer Conference, 1992.
• Mason, R. E., B. Matthews, and M. S. El-Genk, "Constitution of Nuclear Fuel and Fission Products with Refractory Alloys". Trans. Am. Nucl. Soc., 1991 Annual Meeting,, 1991.
• Guo, Z., and M.S. El-Genk, "Effect of Surface Orientation on Boiling Heat Transfer". Trans. Am. Nucl. Soc., 64, 1991.
• El-Genk, M.S. and D. Rao, "On the Predictions of Critical Heat Flux in Rod Bundles at Low Flow and Low Pressure Conditions". Int. J. Heat Transfer Engineering, 12(4), 48-57, 1991.
• Chidester, K.M. and R.B. Matthews, "The Role of Carbon Diffusion in Densification of Uranium Dicarbide". Proc. 8th Symposium on Space Nuclear Power Systems, AIP No.217(3), 902-909, 1991.
• Dobranich, D. and M.S. El-Genk, "Thermal Stress Analyses of the Multilayered Fuel Particles of a Particle-Bed Reactor". J. Nuclear Technology, 94, 372-382, 1991.
• El-Genk, M.S. and D.V. Rao, "Buoyancy Induced Instability of Laminar Flows in Vertical Annuli-I. Flow Visualization and Heat Transfer Experiments". Int. J. Heat and Mass Transfer, 33(10), 2145-2159, 1990.
• Rao, D.V. and M.S. El-Genk, "Buoyancy Induced Instability of Laminar Flows in Vertical Annuli-II. Model Development and Analysis". Int. J. Heat and Mass Transfer, 33(10), 2161-2172, 1990.
• 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, 1990.
• Rao , D. V. and M. S. El-Genk, "Critical Heat Flux Predictions for the Upgrade of Sandia's Annular Core Research Reactor". Institute for Space Nuclear Power Studies, Final Report No. ISNPS - 312631-1-90, 1990.
• Rao , D. V. and M. S. El-Genk, "Critical Heat Flux Predictions for the Upgrade of Sandia's Annular Core Research Reactor". Institute for Space Nuclear Power Studies, Final Report No. ISNPS - 312631-1-9, 1990.
• El-Genk, M.S. and D. Rao, "Critical Heat Flux Predictions in Multi-Rod Bundles at Low Flow and Low Pressure Conditions". Thermal Hydraulics of Advanced Nuclear Reactors, HT-150 ASME, 20-30, 1990.
• El-Genk, M.S., S.D. Bedrose, and D.V. Rao, "Forced and Combined Convection of Water in a Vertical Seven-rod Bundle with P/D=1.38". Int. J. Heat and Mass Transfer, 33(6), 1289-1297, 1990.
• El-Genk, M.S., S.D. Bedrose, and D.V. Rao, "Forced and Combined Convection of Water in Rod Bundles". Heat Transfer Engineering, 11(4), 32-43, 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, 1990.
• Dobranich, D. and M.S. El-Genk, "Thermal Stress Analysis of the Multilayered Spherical Fuel Particles of a Particle Bed Space Nuclear Reactor". ASME Annual Winter Meeting, Paper No-90-WA/NE-2, 1990.
• Rao, D.V., M.S. El-Genk, and A.J. Juhasz, "Transient Model of High Temperature Heat Pipes". Proc. 7th Symposium on Space Nuclear Power Systems, 854-861, 1990.
• Ross, S.B., M.S. El-Genk, and R.B. Matthews, "Uranium Nitride Fuel Swelling Correlation". J. Nuclear Materials, 170, 169-177, 1990.
• El-Genk, M.S., S.D. Bedrose, and D.V. Rao, "Forced Laminar and Combined Downflow in Multirod Bundles". Trans. American Nuclear Society, 60, 674-676, 1989.
• , "Heat Transfer Experiments of Forced and Combined Downflows of Water in a Seven-Rod Bundle". Porous Media, Mixtures, and Multiphase Heat Transfer, HTD-117, 15-21, 1989.
• Seo, J.T. and M.S. El-Genk, "Image Analysis Technique for Porosity Determination of Carbide Fuel". Space Nuclear Power Systems 1988, Orbit Book Company, 419-428, 1989.
• Rao, D.V. and M.S. El-Genk, "Transition to Buoyancy Induced Turbulent Flow in Vertical Annuli". ASME Annual Winter Meeting, 1989.
• Ross, S.B., M.S. El-Genk, and R.B. Matthews, "A Comparison of the Swelling Behavior of UN and (U,Pu)C Fuels". Trans. 5th Symposium on Space Nuclear Power Systems, 547-551, 1988.
• Amos, C., V. Denny, M. S. El-Genk, J. Maly, P. Mast, A. Mertol, B. Rothleder, R. Sartor, J. Weingardt, and K. Williams, "A Methodology to Examine In-Vessel Phenomena for use in the SRP Reactor Level 2 Probabilistic Risk Assessment". SAIC. Report, 1988.
• Richardson, J. and M. S. El-Genk, "Coolability Studies of Dual-Layered Particle Beds". Particulate Phenomena and Multi-Phase Transport, 3, 315-328, 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, 2, 377-402, 1988.
• Kim, S.-H. and M.S. El-Genk, "Experimental Heat Transfer Studies for Low Flow of Water in Rod Bundles". Proc. 1988 National Heat Transfer Conference, HTD-96(2), 285-292, 1988.
• 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, 225-243, 1988.
• El-Genk, M.S., S.J. Haynes, and S.-H. Kim, "Experimental Studies of Critical Heat Flux for Low Flow of Water in Vertical Annuli at Near Atmospheric Pressure". Int. J. Heat and Mass Transfer, 31(11), 2291-2304, 1988.
• 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.
• 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, 1988.
• 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, 3, 107-120, 1988.
• Ross, S.B., M.S. El-Genk, and R.B. Matthews, "Thermal Conductivity Correlations for Uranium Nitride Fuel Between 10 K and 1923 K". Journal of Nuclear Materials, 151, 313-317, 1988.
• Rao, D.V., M.S. El-Genk, R. A. Rubio, J. W. Brayson, and F. C. Foushee, "Thermal-Hydraulic Model for the Sandia's Annular Core Research Reactor". Proc. .11th TRIGA Owner User Conference, 1988.
• Louie, D. L. Y., M. S. El-Genk, R. L. Petty, and R. B. Matthews, "Characterization of ( U ,Pu)C Fuel Pin's Swelling Behavior". Am. Cer. Soc. 89th Annual Meeting, 1987.
• Louie, D. L. Y. and M.S. El-Genk, "Characterization of Fuel Swelling in Helium-Bonded (U, Pu )C Fuel Pins". Technical Report LANL-727-1, Final Report No. NE-116 (87), 1987.
• El-Genk, M. S., Sung-Ho Kim and G. M. Zaki, "Experimental Heat Transfer Studies of Free Convection of Atmospheric Air in Vertical Open Annuli for Application to Air Coolability of TRIGA Type Reactors". SNL-417-1, Report No. NE 122(87), 1987.
• 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". SNL-417-1, Report No. NE-125 (87), 1987.
• 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.
• El-Genk, M.S. and D. V. Rao, "Heat Transfer Experiments and Correlations for Low Reynolds Number flows of water in vertical annuli". Report No. NE-124 (87), SNL-417-1, 1987.
• El-Genk, M. S. and D. V. Rao, "Heat Transfer Experiments of Unstable, Buoyancy Assisted and Opposed Laminar Flows in a Vertical Annulus". SNL-417-1, Report No. NE-123 (87), 1987.
• El-Genk, M.S., R.B. Matthews, and S.G. Bankoff, "Molten Fuel-Coolant Interaction Phenomena with Application to Carbide Fuel Safety". Progress in Nuclear Engineering, 20(3), 151-198, 1987.
• El-Genk, M.S., S. Ross, and R.B. Matthews, "Uranium Nitride Fuel Swelling and Thermal Conductivity Correlations". Trans. 4th Symposium on Space Nuclear Power Systems, 313-317, 1987.
• 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, 1986.
• Louie, D. L. Y., M. S. El-Genk, R. L. Petty, R. B. Matthews, and J. H. Cook, "Image Analysis Technique for Porosity Determination of Carbide Fuel". Am. Cer. Soc. 88th Annual Meeting, 1986.
• Zaki , G. M., M. S. El-Genk, and J. S. Philbin, "Natural Convection Heat Transfer with Application to the Annular Core Research Reactor (ACRR)". Sandia National Labs, SAND85-2073, 1986.
• El-Genk, M.S. Sung-Ho Kim, G. M. Zaki, F. C. Foushee, J. S. Philbin, and J. Schultze, "On the Air Coolability of TRIGA Reactors Following a Loss of Coolant Accident". Proc. 10th TRIGA Owner-User Conference, 1986.
• El-Genk, M.S. and R. B. Matthews, "Review of Molten Fuel/Coolant Interaction Phenomena with Applciation to Carbide Fuel Safety". Los Alamos Report, LA-10477, 1986.
• Louie, D. L. Y. and M. S. El-Genk, "Characterization of Carbide Fuel Irradiation and Swelling Behavior". LANL-112-1, Report No. NE-111 (85), 1985.
• 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, 42, 113-120, 1985.
• El-Genk, M.S., S. Kim, and D. Erickson, "Sedimentation of Binary Mixtures of Particles of Unequal Densities and of Different Sizes". Chem. Eng. Commun., 36, 99-119, 1985.
• El-Genk, M.S. and S.-H. Kim, "Experimental Studies of Lateral Distribution and Composition of Sediments of Single and Binary Particle Mixtures". AIChE Symposium Series-Heat Transfer, 225(79), 372, 1984.
• Kim, S.-H. and M.S. El-Genk, "Experimental Studies of Lateral Variation of Height and Composition of Particle Beds". Trans. American Nuclear Society, 46, 487-488, 1984.
• El-Genk, M. S. and Sung-Ho Kim, "On the Composition of Core Debris Beds During a Severe Core Damage Accident". Trans. Am. Nucl. Soc., 47, 310-312, 1984.
• El-Genk, M.S., S.-H. Kim, and D. Erickson, "Post-Accident Heat Removal Analysis: An Assessment of the Composition of Core Debris Beds". Proc. 5th International Meeting on Thermal Nuclear Reactor Safety, 1984.
• Sung-Ho Kim and M. S. El-Genk, "Settling Studies of Single and Two-Component Mixtures of Metal Spheres". SURP-195-6, Report No. NE-98 (83), 1984.
• El-Genk, M.S., R.M. Kumar, and D.W. Croucher, "An Analysis of Prompt Fission Gas Release from a Cladding Breach". J. Nuclear Technology, 60, 291-303, 1983.
• El-Genk, M.S. and R. Coen, "Characterization of vapor explosion fragments: Permeability Measurements in Mixed and Stratified Beds". Report NO. NE-95 (83, SNL-162-1, 1983.
• El-Genk, M.S., D. Louie, E. Bergeron, and D. Mitchell, "Dependence of Porosities and Capillary Pressures in Particle Beds on the Morphology and the Size of the Particle". AIChE Symposium Series-Heat Transfer, 225(79), 256, 1983.
• El-Genk, M. S. and E. Bergeron, "Dryout Heat Flux in Particulate Beds of Steel Grit". Trans. Am. Nucl. Soc., 44, 377, 1983.
• El-Genk, M. S., D. Louie, R. J. Lipinski, and D. E. Mitchell, "Experimental Measurements of Porosity and Capillary Pressure in Particulate Beds". Trans. Am. Nucl. Soc., 44, 337, 1983.
• El-Genk, M.S., R.R. Hobbins, and P.E. MacDonald, "Fragmentation of Molten Debris During a Molten Fuel-Coolant Interaction". J. Nuclear Materials, 113, 101-117, 1983.
• El-Genk, M.S. and R.L. Moore, "An Analysis of Molten Debris Freezing and Wall Erosion in a Severe RIA Test". Proc. 19th National Heat Transfer Conference, OSTI ID: 5247715, 30133, 1982.
• El-Genk, M. S. and D. Louie, "Porosities and Capillary Heads Measurements in Particulate Beds". SURP-080-6, Report. No. NE-94 (82), 1982.
• El-Genk, M.S., R. M. Kumar, D. W. Croucher, "An Evaluation of Prompt Release of Fission Gas from a Breached Cladding". Trans. Am. Nucl. Soc., 37, 1981.
• El-Genk, M.S. and R.R. Hobbins, "Analysis of Molten Fuel-Coolant Interaction During a Reactivity Initiated Accident Experiment". Fuel-Coolant Interaction, 19, 1981.
• El-Genk, M.S. and R. M. Kumar, "Analysis of Prompt Fission Gas Release from a Breached Fuel Rod". EGG-TFBP-5561, 1981.
• El-Genk, M.S., R.R. Hobbins, and P.E. MacDonald, "Molten Fuel-Coolant Interaction During a Reactivity Initiated Accident Experiment". J. Nuclear Engineering and Design, 66, 247-267, 1981.
• El-Genk, M.S. , "Molten Fuel-Coolant Interaction Occurring in a Severe Reactivity Initiated Accident Experiment". NUREG/CR-1900, EGG-2080, 1981.
• El-Genk, M.S. and R.L. Moore, "Transient Debris Freezing and Potential Wall Melting During a Severe Reactivity Initiated Accident Experiment". J. Nuclear Technology, 53, 354-373, 1981.
• El-Genk, M.S. and R. L. Moore, "A Study of Molten Debris Freezing and Wall Erosion in the RIA-ST-4 Experiment". NUREG/CR-1072, EGG-2020, 1980.
• El-Genk, M. S. and R. L. Moore, "An Assessment of Molten Debris Freezing in a Severe RIA In-Pile Test". Trans. Am. Nucl. Soc., 34, 482, 1980.
• El-Genk, M. S., "Effect of Coolant Conditions on Core Pressurization During an Energetic MFCI in LWRs". Trans. Am. Nucl. Soc., 35, 390, 1980.
• El-Genk, M. S., "Fragmentation Mechanisms Occurring During an Energetic Fuel-Coolant Interaction". Trans. Am. Nucl. Soc., 35, 348, 1980.
• El-Genk, M. S., "On a Vapor Explosion in the RIA-ST-4 Experiment". Trans. Am. Nucl. Soc., 34, 472, 1980.
• El-Genk, M. S. and R. L. Moore, "Dual Change-of-Phase in Forced Flow on a Finite Wall with Application to SLSF Safety Analysis". Proc. International Meeting on Fast Reactor Safety, 1979.
• El-Genk, M.S., "Molten Fuel Motion During a High Temperature Transient in LWRs". Trans. Am. Nucl. Soc. , 33, 508, 1979.
• El-Genk, M.S., "Molten Fuel Radial Motion and Cladding Melting During a PCM Event in LWRs". J. Nuclear Engineering and Design, 54, 349-377, 1979.
• El-Genk, M.S. and A.W. Cronenberg, "On the Thermal Stability of a Frozen Crust in Forced Flow on an Insulated Finite Wall". Int. J. Heat and Mass Transfer, 22, 1719-1723, 1979.
• El-Genk, M. S. and D. W. Croucher, "Potential for Fuel Melting and Cladding Thermal Failure During a PCM Event in LWRs". Trans. Am. Nucl. Soc., 33, 506, 1979.
• El-Genk, M.S. and A.W. Cronenberg, "Solidification in a Semi-Infinite Region with Boundary Conditions of the Second Kind: An Exact Solution". Letters in Heat and Mass Transfer, 6, 321-327, 1979.
• El-Genk, M.S. and A.W. Cronenberg, "Some Improvements to the Solution of Stefan-Like Problems". Int. J. Heat and Mass Transfer, 22, 167-170, 1979.
• El-Genk, M.S. and A.W. Cronenberg, "Stefan-Like Problems in Finite Geometry". AIChE Symposium Series Heat Transfer No. 189, 69, 1979.
• Cronenberg, A.W. and M.S. El-Genk, "A Diffusion Model for UO2-Zircaloy Interaction". Proc. 4th Int. Conf. on Zirconium in the Nuclear Industry, 1978.
• El-Genk, M.S. , "An Asessment of Fuel Melting, Radial Extrusion, and Cladding Thermal Failure during a Power-Cooling-Mismatch Event in Light Water Reactors". NUREG/CR-0500, TREE-1270, 1978.
• El-Genk, M.S. and A.W. Cronenberg, "An Assessment of Fuel Freezing and Drainage Phenomena in a Reactor Shield Plug Following a Core Disruptive Accident". J. Nuclear Engineering and Design, 47, 195-225, 1978.
• Cronenberg, A.W. and M.S. El-Genk, "An Assessment of Oxygen Diffusion During UO2-Zircaloy Interaction". J. Nuclear Materials, 78, 390-407, 1978.
• El-Genk, M.S. and A. W. Cronenberg, "Improvements to the Solution of Stefan-Like Freezing and Melting Problems with Application to LMFBR Safety Analysis". Technical Report (Final) No. NE-52 (78), NRC-318-1, 1978.
• El-Genk, M. S. and A. W. Cronenberg, "Assessment of Molten Fuel Motion in CRBR Shield Plug Following a Core Disruptive Accident". Trans. Am. Nucl. Soc., 26, 371, 1977.