Latest Publications

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.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
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, 2023. 1-27
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, 2023. 1-25
El-Genk, M.S., T. Schriener, Cybersecurity Analyses of a Space Reactor Power System under Simulated False Data Injection Attacks. Proceedings AIAA ASCEND Conference, 2023.
El-Genk, M.S., T. Schriener, Design and Analyses of Lightweight Radiator Module for Nuclear Reactor Lunar Surface Power. Proceedings AIAA ASCEND Conference, 2023.
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, 2022. 11:04 1-14
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, 2022. 143 103783

Recent Events

8/15/2023
Graduate Research Assistantships Available Fall 2023 at UNM-ISNPS
7/28/2023
Doctoral Graduation - Ragai Altamimi
1/17/2023
UNM, Purdue work to develop autonomous control architecture for microreactors
11/25/2022
First Year Progress Report for NASA Advanced Radiator Project

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: A Review of Carbide Fuel Corrosion for Nuclear Thermal Propulsion Applications
Author(s): Pelaccio, D.G., M.S. El-Genk, and D.P. Butt
Journal: Proc. 11th Symposium on Space Nuclear Power and Propulsion
Volume: AIP No.301(2)
Pages: 905-918
Year: 1994

Abstract Link

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