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

Videos

Saturation Boiling Videos

ISNPS is currently investigating pool boiling of dielectric liquids as a method of cooling high powered electronics in anticipation of the development of more powerful and compact computers. Using porous graphite and finned copper surfaces, heat fluxes in excess of 70 W/cm2 have been dissipated in boiling of HFE-7100. To explore the effect that various parameters have on boiling heat transfer, experiments are performed using different liquids (HFE-7100 and FC-72), at different subcoolings (0 K to 30 K subcooling), different surface orientations (0° to 180°), and on different surfaces (plane and finned surfaces made of copper and porous graphite). Still images and video helps to understand and explain the boiling phenomena. Below are links to videos of showing pool boiling under several different conditions.