- 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
Quoc Duong
Research Assistant
Research Topic: Small Modular Reactor (SMR) - Core Neutronics Parametric Analyses
Graduate Student working toward M.S.
Education
- B.S. Nuclear Engineering, University of New Mexico, May 2019
- Graduate student working toward M.S. Nuclear Engineering, University of New Mexico
Research Projects
Quoc Duong's research is related to the Very-Small, Long -Life, Modular (VSLLIM) reactor previously developed at the Institute for Space and Nuclear Power Studies, University of New Mexico. His focus is to investigate the core neutronics analyses of heterogenous UN (uranium nitrite) and ThN (thorium nitrite) fuel in application to VSLLIM reactor. Part of the research is to estimate the operation lifetime at 10-MW thermal power and post operation radiological source term/dose rate for the VSLLIM reactor with heterogenous Uranium-Thorium based fuel.
Besides, Quoc Duong as well participates in the research team at ISNPS on the research topic of Nuclear CyberSecurity. The research is focusing on developing and testing the LOBO Nuclear CyberSecurity (NCS) Platform in application to nuclear power plant developed at the Institute for Space and Nuclear Power Studies (ISNPS).
Contact
List of Publications
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