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

Publication Details

Title: Fluid Flow and heat Transfer Analysis of the VHTR Lower Plenum Using the FUEGO CFD Code
Author(s): Rodriguez, S. B., S. Domino and M. S. El-Genk
Journal: Proceedings CFD for Nuclear Reactor Safety (CFD4NRS-3)
Year: 2010

Abstract Link

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