Latest Publications

El-Genk, M.S., T. Schriener, Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface. J. Nuclear Technology, 2025. 211(3) 400-428
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.
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.
El-Genk, M.S., T.M. Schriener, Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface. Nuclear Technology, 2024. 1-29
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. Schriener, Lightweight Heat Pipe Radiator Panel for Lunar Surface Fission Power Systems. Proceedings AIAA ASCEND Conference, 2024.
El-Genk, M.S., Designs of Space Nuclear Reactor Power Systems for the Avoidance of Single Point Failures, Launch Safety, and a Long Operation Life. Proceedings AIAA ASCEND Conference, 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

Recent Events

10/4/2024
ISNPS Director Mohamed El-Genk invited to be Panelist at Opening Plenary of 2024 ANS Winter Conference and Expo
12/4/2024
El-Genk invited speaker at the Open Plenary Panel at ANS Winter Meeting, 17-21, 2024
12/9/2024
Masters Graduation - Ahmad Shaheen

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

Online: Contact Form

Publications By Year : 1981

Showing 6 results

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.

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