Latest Publications

El-Genk, M.S., T.M. Schriener, K. Kresl-Hotz, Simulation of Liquid Mixing and Stratification in Upper Plenum of Pool-Type Sodium Fast Reactors Following Sudden Decrease in Power or Scram. J. Nuclear Technology, 2026. 1-28
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.
Schriener T.M., M.S. El-Genk, Armoring Lightweight Foldable Radiator Panel for Lunar Surface Fission Power Systems. J. Nuclear Technology, 2025. 1-25
Schriener T.M., M.S. El-Genk, Launch Solid Stress Analyses of Ultra-Light Heat Rejection Radiator Module and Panel for Lunar Fission Surface Power. J. British Interplanetary Society, 2025. 78(3) 74-83
El-Genk, M.S., T.M. Schriener, A.N. Shaheen, Machine-Learning Algorithms for Remote-Control and Autonomous Operation of the Very-Small, Long-Life, Modular (VSLLIM) Microreactor. J. Nuclear Engineering, 2025. 6(4) 54
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.

Recent Events

4/6/2026
Masters Graduation - Keenan Kresl-Hotz
9/12/2025
Seniors in the in the Nuclear Engineering Department visit the UNM-ISNPS Lab
4/17/2025
ISNPS Graduate Student Keenan Kresl-Hotz Awarded for Presentation at ANS 2025 Student Conference

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 : 1983

Showing 7 results

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 E. Bergeron, "Permeability Measurements in Mixed and Stratified Particle Beds". Proc. Int. Meeting on Light Water Reactor Severe Accident Evaluation, 1983.

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