Latest Publications

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.
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.
El-Genk, M.S., Designs of Space Nuclear Reactor Power Systems for the Avoidance of Single Point Failures, Launch Safety, and a Long Operation Life. Proceedings AIAA ASCEND Conference, 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

Recent Events

10/4/2024
ISNPS Director Mohamed El-Genk invited to be Panelist at Opening Plenary of 2024 ANS Winter Conference and Expo
12/4/2024
El-Genk invited speaker at the Open Plenary Panel at ANS Winter Meeting, 17-21, 2024
12/9/2024
Masters Graduation - Ahmad Shaheen

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 : 1984

Showing 8 results

Louie, D.L.Y., and M.S. El-Genk, "Consequences of Venting System Failure in the Heat Pipe Space Nuclear Reactor". Trans. 1st Symposium on Space Nuclear Power Systems, SR-10, 1984.
Dean, V. F. , M. S. El-Genk, D. L. Louie, and D. M. Woodall, "Design Status of the SP-100 Heat Pipe Space Nuclear Reactor System". AFWL-144-1, Report No. NE-101 (84), 1984.
El-Genk, M.S. and S.-H. Kim, "Experimental Studies of Lateral Distribution and Composition of Sediments of Single and Binary Particle Mixtures". AIChE Symposium Series-Heat Transfer, 225(79), 372, 1984.
Kim, S.-H. and M.S. El-Genk, "Experimental Studies of Lateral Variation of Height and Composition of Particle Beds". Trans. American Nuclear Society, 46, 487-488, 1984.
Louie, D., M. S. El-Genk, and S. Wright, "Fission Gas Release-Venting Model for Space Nuclear Reactors". Trans. Ist Symp. On Space Nuclear Power Systems, CONF-840113, 1984.
El-Genk, M. S. and Sung-Ho Kim, "On the Composition of Core Debris Beds During a Severe Core Damage Accident". Trans. Am. Nucl. Soc., 47, 310-312, 1984.
El-Genk, M.S., S.-H. Kim, and D. Erickson, "Post-Accident Heat Removal Analysis: An Assessment of the Composition of Core Debris Beds". Proc. 5th International Meeting on Thermal Nuclear Reactor Safety, 1984.
Sung-Ho Kim and M. S. El-Genk, "Settling Studies of Single and Two-Component Mixtures of Metal Spheres". SURP-195-6, Report No. NE-98 (83), 1984.

Go Back