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 : 1978

Showing 5 results

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.

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