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Dr. Saeed Alameri
Dr. saeed alameri Assistant Professor Center Director Mechanical & Nuclear Engineering

Contact Information
saeed.alameri@ku.ac.ae +971 2 312 4183

Biography

Dr. Saeed Alameri obtained his bachelor’s degree in electrical engineering from United Arab Emirates University in 2008 and continued his postgraduate studies to obtain a master’s and doctorate degree in nuclear engineering from the Colorado School of Mines in the United States of America in 2012 and 2015, respectively. Dr. Alameri specializes in nuclear reactor physics and nuclear fuel materials and has more than 10 years of experience in research and development. Dr. Alameri’s research areas focus on nuclear reactor design, advanced nuclear fuel concepts, and looking for improved safety and security of nuclear reactors. He has participated in organizing and evaluating many international conferences in the fields of advanced nuclear reactors and accident-resistant nuclear fuels. Dr. Alameri currently holds several positions; including Director of the Emirates Nuclear Technology Center (ENTC), Manager of the Gulf Nuclear Energy Infrastructure Institute (GNEII), member of the National Committee for Radiation Protection (RPC), and Assistant Professor in the Department of Mechanical & Nuclear Engineering at Khalifa University. He is also the Theme 4 Lead of the Emirates Nuclear Technology Center. Dr. Alameri is supervising a group of graduate students in the Department of Mechanical and Nuclear Engineering at Khalifa University and a specialized research team at the ENTC to investigate various aspects of the Advanced Power Reactor (APR1400) to achieve a safer and more reliable operation.


Education
  • PhD, Nuclear Engineering, Colorado School of Mines (USA), 2015
  • MEng, Nuclear Engineering, Colorado School of Mines (USA), 2012
  • BSc, Electrical Engineering, UAE University (UAE), 2008

Teaching
  • Nuclear Reactor Physics
  • Nuclear Systems Design and Analysis
  • Safety Analysis for Nuclear Power Plants

Affiliated Centers, Groups & Labs

Research
Research Interests
  • Nuclear Reactor Fuel
  • Reactor Kinetics and Transients Modeling
  • Advanced Nuclear Technology

Research Projects

The safe, reliable, and economic operation of the UAE’s nuclear power plants at Barakah has been at the heart of the nation’s nuclear energy program since its inception in 2008 with the publication of the “UAE Policy on the Peaceful Use of Nuclear Energy” document. Following the events at Fukushima, Accident Tolerant Fuels (ATFs) became a focus within the nuclear fuel R&D community. Using ATFs in the existing APR1400 Barakah reactors would help endure loss of active cooling in the reactor core for a considerably longer period of time, and therefore would be safer, than the current fuel system while maintaining or improving performance during normal operations. To achieve this goal, many assessments will be needed including neutronics, thermal-hydraulic, thermo-mechanical/chemical, and fuel performance analyses for several candidate ATF concepts. In performing final assessments, the “do no harm” principle will be observed, meaning that the selected ATF concepts must, under all operating conditions, perform as well as or better than the current fuel system used in the APR1400 reactor core.

This project aims at developing a new Cr-coating technique on Zr alloy cladding. To protect the Zr alloy substrate and improve the oxidation resistance of cladding during severe accidents, it is desirable to apply Cr-coating to both of the outer and inner surface of Zr alloy cladding tube. In this project, a single-pot electrodeposition Cr/Nb coating technique will be developed, which enables to coat both the sides of Zr alloy cladding tube. A thin layer with Nb will be introduced to avoid any defects at the interface between Cr and Zr alloy. The coating adhesion between surface layers will be examined using SEM and TEM. Also, the oxidation behavior of Cr/Nb-coated Zr alloy fabricated by the new technique will be evaluated in high temperature air and steam conditions. Also, the performance of UO2 fuel with Cr/Nb-coated cladding will be evaluated using the software and tools available at the ENTC. This includes neutronic and thermal-hydraulic evaluations to study the performance and behavior of the new fuel system against the reference fuel-zircaloy system. 

The main goal of the project is to develop tensor-network algorithms for solving the neutron transport equation (NTE) in regimes relevant to reactor physics simulations. Our main long-term motivation for this is to combine the improved NTE solvers with state-of-the-art optimization methods to attain better optimization schemes for the fuel-assemblies shuffling. We aim at proof-of-concept demonstrations of computational advantages over traditional classical algorithms. This will in turn set the bases for not only fully-quantum algorithms but also the development of industrial-level software, which would be tackled in follow-up phases of this first project.


Research Staff and Graduate Students:

Staff
Mohammad Alrwashdeh Research Scientist
Khurrum Saleem Chaudri Post Doctoral Fellow
Moahmed Lahdour Post Doctoral Fellow
Students
Abdulla Alnuaimi PhD student
Maithah Alaleeli PhD student
Salem Almessabi MSc student
Asma Alzarooni MSc student
Nouf Alhattawi MSc student
Hasan Alnuaimi MSc student