- 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
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
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
Education
- B.S. Nuclear Engineering, UNM, 2010
- M.S. Nuclear Engineering, UNM, 2015
Research Project
Luis is pursuing research regarding the Scalable LIquid Metal cooled small Modular (SLIMM). SLIMM is a natural circulation, sodium cooled reactor that will provide power from 10s to a few 100s MWe to small or isolated communities. The advantages of this reactor include its capabilities to be built and assembled in the factory and shipped to the construction site by rail, heavy trucks, or on barges, and at its end of life it could be easily replaced by a new unit. Luis' research involves thermal-hydraulic modeling of the reactor, natural circulation system, neutronics, and the passive system of decay heat removal after shutdown.
The analysis of the SMR is carried out using the Computation Fluid Dynamics packages STAR-CCM+ and SolidWorks Simulation for the thermal-hydraulics, Monte Carlo radiation transport code MCNP6 for the neutronics, and MATLAB for the transient analysis of the decay heat removal.
Contact
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