Publications & Patents - Khalifa University

Publications

Publications

Year 2025

M. Amer, et al., “comprehensive review, CFD and ML analysis of flow around tandem circular cylinders at sub-critical Reynolds numbers”, doi:https://doi.org/10.1016/j.jweia.2024.105998
M. Faizan, and I. Afgan, “Dynamic Assessment and Optimization of Thermal Energy Storage Integration with Nuclear Power Plants Using Machine Learning and Computational Fluid Dynamics”, doi:https://doi.org/10.1016/j.apenergy.2025.125939
S. Osman, et al., “Heat transfer correlations for curved downward-facing surfaces in forced and mixed convection regimes”, doi:https://doi.org/10.1063/5.0250537
S. Albdour, et al., “Thermal performance analysis of reflux condensation in vertical tubes via pure steam” doi:https://doi.org/10.1007/s42757-024-0234-x
A. Alsaleh, et al., “Estimation of soil organic carbon in arid agricultural fields based on hyperspectral satellite images”, doi:https://doi.org/10.1016/j.geoderma.2024.117151
F. Almazrouei, et al., “Numerical Study of Near-Field Radionuclides Dispersion Around Barakah Power Plant During Postulated Accidental Release Scenarios” doi:https://doi.org/10.1007/s13369-024-09734-8
J. Mihalik et al., “Leaching characteristics of strontium from gypsum soil and calcareous sand present in saline land in arid regions: consequences for migration of radiostrontium”, doi:https://doi.org/10.1016/j.scitotenv.2025.179553
M.P. Subeesh et al., “Seasonality of Internal Tides in the Strait of Hormuz: Observations and Modeling” doi:https://doi.org/10.1029/2024JC021007
K. Karrupasamy et al., “Critical evaluation of accident tolerant fuel selection criteria for APR- 1400 nuclear reactors”, doi:https://doi.org/10.1080/23746149.2024.2435273
J. Ubaid, et al., “Burst Safety Analysis of Strengthened FeCrAl Claddings in APR1400 Fuel Rods Subject to LOCA Conditions” doi:https://doi.org/10.1002/ese3.2038
J. Mun, et al., “Advanced fuel performance analysis of multi-layered coated accident-tolerant fuel (ATF) cladding using a coupled multiphysics approach” doi:https://doi.org/10.1016/j.net.2025.103549
B. Abdu, et al., “Microbial kinetics of aerobic and anoxic ethanolamine biodegradation: Substrate and free nitrous acid inhibition”, doi:https://doi.org/10.1016/j.jwpe.2025.107448
H. Alnuaimi, et al., “Part Strength Control Element Assemblies Effectiveness in APR1400 Reactivity Management During Transient Operation” doi:https://doi.org/10.1007/s13369-023-08222-9
M. Alrwashdeh and S. Alameri, “A Neutronics Study of the Initial Fuel Cycle Extension inAPR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design”,doi:https://doi.org/10.1007/s13369-023-07905-7

Conference Papers:

F. Gafoor, et al., “High-resolution monitoring and modelling of thermal plumes from nuclear power plants in the Arabian Gulf”, doi:https://doi.org/10.1117/12.3046095

Year 2024

G. Hegab, et al., “Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond,” Alexandria Engineering Journal, doi: https://doi.org/10.1016/j.aej.2024.07.041.
B. Li, et al., “Dynamics of PCM melting driven by spatially varying heat load,” International communications in heat and mass transfer, doi:https://doi.org/10.1016/j.icheatmasstransfer.2024.107735.
Muhammad, et al., “Thermal energy storage integration with nuclear power: A critical review,” Journal of Energy Storage, , doi: https://doi.org/10.1016/j.est.2024.112577.
R. Selvakumar and A. Alkaabi, “Design and performance evaluation of a novel electrohydrodynamically enhanced PCM heat sink,” Journal of Energy Storage, doi: https://doi.org/10.1016/j.est.2024.112375.
K. Chaudri, et al., “Review of Neutron Physics Analyses for Accident-Tolerant Fuel System,” Engineered science, doi: https://doi.org/10.30919/es1126.
R. Bose, et al., “Self-Ordered Anodic Porous Oxide Layers as a High Performance Electrocatalyst for Water Oxidation,” ACS Applied Energy Materials, doi: https://doi.org/10.1021/acsaem.4c00305.
I. Khurshid, et al., “Study on corium-concrete interaction, heat transfer, and concrete ablation: Impact of replacing Zircaloy cladding with accident tolerant silicon carbide cladding on corium characteristic,” Applied Thermal Engineering, doi: https://doi.org/10.1016/j.applthermaleng.2024.122569.
S. A. Albdour, et al., “Machine learning-driven approach for predicting the condensation heat transfer coefficient (HTC) in the presence of non-condensable gases,” International Journal of Heat and Fluid Flow, doi: https://doi.org/10.1016/j.ijheatfluidflow.2024.109330.
Y. Addad, et al., “Effectiveness re-evaluation on the intentional primary system depressurization during Zion-like Westinghouse PWR station blackout considering pressure dependence of radionuclides release,” Nuclear Engineering and Design, doi:https://doi.org/10.1016/j.nucengdes.2023.112895.
Y. Ismail, et al., “Iodide ion-imprinted chitosan beads for highly selective adsorption for nuclear wastewater treatment applications,” Heliyon, doi: https://doi.org/10.1016/j.heliyon.2024.e24735.
H. Mittal, et al., “Recent developments in the adsorption of uranium ions from wastewater/seawater using carbon-based adsorbents,” Journal of environmental chemical engineering, doi: https://doi.org/10.1016/j.jece.2023.111705.
S. Osman, et al., “Experimental study of boiling heat transfer of inclined down-ward facing heated curved wall under low flow and pressure conditions,” Applied Thermal Engineering, doi: https://doi.org/10.1016/j.applthermaleng.2023.121706.
B. Li, et al., “Velocity field measurement and heat transfer characteristics of the melting process under constant heat flux,” International Journal of Heat and Mass Transfer, doi: https://doi.org/10.1016/j.ijheatmasstransfer.2024.125636
S. Albdour, et al., “Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research,” International Journal of Energy Research, doi: https://doi.org/10.1155/2024/2880812.
S. Albdour, et al., “A Predictive Machine Learning-Based Analysis for In-Tube Co-current Steam Condensation Heat Transfer in the Presence of Non-condensable Gases,” Arabian Journal for Science and Engineering, doi: https://doi.org/10.1007/s13369-024-08986-8.
S. Rabbani, et al., “Graphene-nuclear nexus: a critical review,” *2D Materials, doi: https://doi.org/10.1088/2053-1583/ad5bf0.
A. Alzarooni, et al., “Review of Neutronics, Thermal-Hydraulic, and Fuel Performance Research of Accident Tolerant Fuels for APR-1400 in United Arab Emirates Nuclear Power Plants,” in *Lecture Notes in Mechanical Engineering, doi: https://doi.org/10.1007/978-3-031-64362-0_25
S. Prakash and Y. Addad, “A comprehensive examination of the linear and numerical stability aspects of the bubble collision model in the TRACE-1D two-fluid model applied to vertical disperse flow in a PWR core channel under loss of coolant accident conditions” doi: https://doi.org/10.1016/j.net.2024.02.057
J. Ubaid, et al., “Thermomechanical analysis of SiC-based duplex claddings with varying thickness ratio for accident-tolerant nuclear fuel systems” doi: https://doi.org/10.1016/j.ecmx.2024.100672
M. Faizan, et al., “Influence of variable gravity on the phase change material for enclosed vertical channels with helical fins” doi: https://doi.org/10.1016/j.applthermaleng.2024.123494
Mihalik, J., et al., “Challenges in radioecology following the new trends in UAE’s agriculture and environmental changes”: doi: https://doi.org/10.1007/s11356-024-35139-z
R. Deepak, et al., “Melting kinetics of PCM under synergistic effects of passive nanoparticle addition and active electric field exposure”: doi: https://doi.org/10.1016/j.ecmx.2024.100810
R. Bose, et al., “Stainless steel-derived nano-porous oxide: a cost-efficient, stable, and corrosion-resistant hydrogen evolution catalyst” doi: https://doi.org/10.1039/d4ta03317e
S. Albdour, et al., “A critical review on the charging and transport dynamics of atmospheric radioactive aerosols: Fundamentals and advances” doi: https://doi.org/10.1016/j.scitotenv.2024.177130
M. Alrwashdeh and S. Alameri, “Correction: Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core” doi: https://doi.org/10.3390/en17102293
S. Albdour, et al., “Derivation of a Condensation Heat Transfer Model for Light Water Reactor Applications Using Machine Learning Techniques” doi: https://doi.org/10.1007/978-3-031-64362-0_49
S. Osman, et al., “Modeling and Assessment for the Estimation of Heat Transfer Coefficients on Curved Downwards-Facing Heated Walls in Application to ERVC” doi: https://doi-org.khalifa.idm.oclc.org/10.1115/VVUQ2024-132689
A. Alzarooni, et al., “Performance Analysis for Enhanced Cr-Coated Fuel Cladding System inAPR-1400 Reactor.” doi: https://doi.org/10.1115/ICONE31-135127
S. Albdour, et al., “Modeling Co-Current and Counter-Current Flow: A PerformanceEvaluation of the TRACE Condensation Model with Non-Condensable and LightGases.” doi: https://doi-org.khalifa.idm.oclc.org/10.1115/ICONE31-134262
S. Saraswat, et al., “Validation and Verification of ASYST Code for Predicting CondensationPhenomena in Nuclear Reactor Safety Systems.” doi: https://doi-org.khalifa.idm.oclc.org/10.1115/ICONE31-134294
R. Shittu et al., “Influence of Mix Design on Chloride Diffusion in Concrete Structures underTemperature Gradient Conditions” doi: https://doi.org/10.11159/icsect24.131
F. Almazrouei, et al., “Towards CFD Predictions of Radioactive Pollutants Dispersion UnderArabian Peninsula Environmental Conditions” doi: https://doi.org/10.1007/978-3-031-64362-0_62

Year 2023

R. Selvakumar, et al., “Melting behavior of an organic phase change material in a square thermal energy storage capsule with an array of wire electrodes,” *Applied Thermal Engineering*, doi: https://doi.org/10.1016/j.applthermaleng.2023.120492.
O. Nesterov, et al., “A numerical assessment of the dispersion of dissolved pollutants in the Arabian Gulf associated with the Barakah nuclear power plant,” *Ocean Modelling*, doi: https://doi.org/10.1016/j.ocemod.2023.102274.
R. D. Selvakumar, et al., “Melting performance enhancement in a thermal energy storage unit using active vortex generation by electric field,” *Journal of Energy Storage*, doi: https://doi.org/10.1016/j.est.2023.107593.
B. Li, et al., “A chitosan film implanted with g-C3N4@Ag nanosheets and in-suit formed AgCl nanoparticles for efficient iodide removal,” *Chemical Engineering Journal*, doi: https://doi.org/10.1016/j.cej.2023.144369.
N. Alhattawi, et al., “Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400,” *Journal of Nuclear Materials*, doi: https://doi.org/10.1016/j.jnucmat.2023.154487.
M. Alrwashdeh, et al., “A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design,” *Arabian Journal for Science and Engineering*, doi: https://doi.org/10.1007/s13369-023-07905-7.
I. Afgan, et al., “Cross flow over two heated cylinders in tandem arrangements at subcritical Reynolds number using large eddy simulations,” *International Journal of Heat and Fluid Flow*, doi: https://doi.org/10.1016/j.ijheatfluidflow.2023.109115.
M. Amidu, et al., “A critical assessment of nanoparticles enhanced phase change materials (NePCMs) for latent heat energy storage applications,” *Scientific Reports*, doi: https://doi.org/10.1038/s41598-023-34907-0.
M. Alaleeli, et al., “The effects of cladding thermo-physical and thermo-chemical properties on the coping time during a PWR unmitigated LB-LOCA,” *Progress in Nuclear Energy*, doi: https://doi.org/10.1016/j.pnucene.2023.104783.
M. Alrwashdeh and S. Alameri, “Extended Fuel Cycles in APR-1400 Reactors: A Neutronics Study,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T128-42085.
R. Shittu, et al., “Chloride Diffusion in Concrete under Temperature Gradient Condition in Arid Climates,” in *International Conference on Civil, Structural and Transportation Engineering*, doi: https://doi.org/10.11159/iccste23.165.
H. Alnuaimi, et al., “Part Strength Control Element Assemblies Effectiveness in APR1400 Reactivity Management During Transient Operation,” *Arabian Journal for Science and Engineering*,. doi: https://doi.org/10.1007/s13369-023-08222-9.
C. Verma, et al., “Coordination bonding and corrosion inhibition potential of nitrogen-rich heterocycles: Azoles and triazines as specific examples,” *Coordination Chemistry Reviews*, doi: https://doi.org/10.1016/j.ccr.2023.215177.
R. Selvakumar et al., “Unipolar Charge Injection Induced Melting Rate Enhancement in a Cylindrical Thermal Energy Storage Unit,” in *Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023*, . doi: https://doi.org/10.13182/NURETH20-40525.
R. Vishnu, et al., “Active vortex generation and enhanced heat transfer in a 3D minichannel by Onsager–Wien effect,” *Applied Thermal Engineering*, doi: https://doi.org/10.1016/j.applthermaleng.2023.121064.
R. D. Selvakumar, et al., “Role of dielectric force and solid extraction in electrohydrodynamic flow assisted melting,” Journal of Energy Storage, doi: https://doi.org/10.1016/j.est.2023.109169.

Year 2022

M. Alrwashdeh, et al., “Review activities of Accident Tolerant Fuel in United Arab Emirates,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T127-39513.
A. Ayodeji, et al., “Deep learning for safety assessment of nuclear power reactors: Reliability, explainability, and research opportunities,” *Progress in Nuclear Energy*, doi: https://doi.org/10.1016/j.pnucene.2022.104339.
I. Khurshid, et al., “Influence of corium temperature, concrete composition and water injection time on concrete ablation during MCCI: New insights,” *Progress in Nuclear Energy*, doi: https://doi.org/10.1016/j.pnucene.2021.104102.
Y. Addad and M. Amidu, “Numerical prediction of slug flow boiling heat transfer in the core-catcher cooling channel for severe accident mitigation in nuclear power plant,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2022.111796.
M. Amidu and Y. Addad, “The influence of the water ingression and melt eruption model on the MELCOR code prediction of molten corium-concrete interaction in the APR-1400 reactor cavity,” *Nuclear Engineering and Technology*, doi: https://doi.org/10.1016/j.net.2021.09.036.
M. Alaleeli, et al., “Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions,” *Energies*, doi: https://doi.org/10.3390/en15145204.
A. Alraisi, et al., “Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis,” *Annals of Nuclear Energy*, doi: https://doi.org/10.1016/j.anucene.2021.108784.
M. Ali, et al., “CFD simulation of an integrated PCM-based thermal energy storage within a nuclear power plant connected to a grid with constant or variable power demand,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2022.111819.
P. A. Rasheed, et al., “Degradation of Concrete Structures in Nuclear Power Plants: A Review of the Major Causes and Possible Preventive Measures,” *Energies*, doi: https://doi.org/10.3390/en15218011.
M. Ali, et al., “Thermal analysis of baffle jetting in fuel rod assembly,” *Physics of Fluids*, doi: https://doi.org/10.1063/5.0109255.
M. Amidu, et al., “Severe accident in high-power light water reactors: Mitigating strategies, assessment methods and research opportunities,” *Progress in Nuclear Energy*, doi: https://doi.org/10.1016/j.pnucene.2021.104062.
N. Nelli, et al., “Characterization of the atmospheric circulation near the Empty Quarter Desert during major weather events,” *Frontiers in Environmental Science*, doi: https://doi.org/10.3389/fenvs.2022.972380.
M. Riahi, et al., “Combined Newton–Raphson and Streamlines-Upwind Petrov–Galerkin iterations for nanoparticles transport in buoyancy-driven flow,” *Journal of Engineering Mathematics*, doi: https://doi.org/10.1007/s10665-021-10205-4.
I. Khurshid, et al.,, “Thermochemical Modeling of Metal Composition and Its Impact on the Molten Corium–Concrete Interaction: New Insights with Sensitivity Analysis,” *Energies*, doi: https://doi.org/10.3390/en15093387.
M. Alaleeli and M. Alrwashdeh, “Neutronics Analysis of Silicon Carbide Composite Sandwich Cladding Design in APR-1400,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T127-39481.
M. Weston, et al., “The First Characterization of Fog Microphysics in the United Arab Emirates, an Arid Region on the Arabian Peninsula,” *Earth and Space Science*, doi: https://doi.org/10.1029/2021EA002032.
P. Raj, et al., “Conceptualization of arid region radioecology strategies for agricultural ecosystems of the United Arab Emirates (UAE),” *Science of the Total Environment*, doi: https://doi.org/10.1016/j.scitotenv.2022.154965.
H. Haddar and M. Riahi, “Eddy-Current Tomographic Inversion Mathematical Tools for Non-Destructive Evaluation of Boiling Tubes,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T127-39789.
M. Amidu, et al., “Sensitivity Analysis of Ex-Vessel Corium Coolability Models in MAAP5 Code for the Prediction of Molten Corium–Concrete Interaction after a Severe Accident Scenario,” *Energies*, doi: https://doi.org/10.3390/en15155370.
R. Abida, et al., “Evaluation of the Performance of the WRF Model in a Hyper-Arid Environment: A Sensitivity Study,” *Atmosphere*, doi: https://doi.org/10.3390/atmos13060985.
M. Jouini and M. Riahi, “Spectral reconstruction of Magnetite deposits in Steam Generator Tubing: An Artificial Intelligence Approach,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T127-39795.
N. Alhattawi and M. Alrwashdeh, “A Sensitivity Analysis for Utilizing Alternative Cladding Materials in APR1400,” *Transactions of the American Nuclear Society*, doi: https://doi.org/10.13182/T127-39460.
M. Alrwashdeh and S. Alameri, “Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core,” *Energies*, doi: https://doi.org/10.3390/en15218008.
M. Ali, et al., “Numerical investigation of a vertical triplex-tube latent heat storage/exchanger to achieve flexible operation of nuclear power plants,” *International Journal of Energy Research*, doi: https://doi.org/10.1002/er.7357.
K. Jena, et al.,”Efficient and cost-effective hybrid composite materials based on thermoplastic polymer and recycled graphite,” *Chemical Engineering Journal*, doi: https://doi.org/10.1016/j.cej.2021.132667.
M. Alrwashdeh and S. A. Alameri, “SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis,” *Energies*, doi: https://doi.org/10.3390/en15103772.
P. Raj, et al., “Transfer of Natural Radionuclides from Soil to Abu Dhabi Date Palms,” *Sustainability (Switzerland)*, doi: https://doi.org/10.3390/su141811327.
B. An, et al., “Effect of Temperature Gradient on Chloride Ion Diffusion in Nuclear Reactor Containment Building Concrete,” *Energies*, doi: https://doi.org/10.3390/en15155581.

Year 2021

S. Olatubosun, et al., “Safety assessment of AP1000: Common transients, analysis codes and research gaps,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2021.111100.
M. Alrwashdeh and S. Alameri, “Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2021.111486.
H. Haddar and M. Riahi, “Near-field linear sampling method for axisymmetric eddy current tomography,” *Inverse Problems*, doi: https://doi.org/10.1088/1361-6420/ac1c50.
I. Khurshid, et al., “A new insight into molten corium concrete interaction with concrete ablation analysis for mitigation scheme,” in *International Conference on Nuclear Engineering, Proceedings, ICONE*, doi: https://doi.org/10.1115/ICONE28-65217.
B. Benaissa, et al., “YUKI Algorithm and POD-RBF for Elastostatic and dynamic crack identification,” *Journal of Computational Science*, doi: https://doi.org/10.1016/j.jocs.2021.101451.
K. Jena, et al., “Comprehensive Review on Concept and Recycling Evolution of Lithium-Ion Batteries (LIBs),” *Energy and Fuels*, doi: https://doi.org/10.1021/acs.energyfuels.1c02489.
O. Al-Yahia, et al., “The feasibility study on development of porous ceramic composites for ion-exchanger,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2021.111329.
M. Amidu, et al., “Numerical investigation of nanoparticles slip mechanisms impact on the natural convection heat transfer characteristics of nanofluids in an enclosure,” *Scientific Reports*, doi: https://doi.org/10.1038/s41598-021-95269-z.
J. Alsuwaidi, et al., “Studies on the optimal mitigation strategy of extended SBO for the isolated multi-unit NPP site,” *Annals of Nuclear Energy*, doi: https://doi.org/10.1016/j.anucene.2021.108615.
O. Nesterov, et al., “Validation and statistical analysis of the Group for High Resolution Sea Surface Temperature data in the Arabian Gulf,” *Oceanologia*, doi: https://doi.org/10.1016/j.oceano.2021.07.001.
M. Ali, et al., “Overall efficiency analysis of an innovative load-following nuclear power plant-thermal energy storage coupled cycle,” *International Journal of Exergy*, doi: https://doi.org/10.1504/IJEX.2021.117606.
R. Bose, et al., “Self-Supportive Bimetallic Selenide Heteronanostructures as High-Efficiency Electro(pre)catalysts for Water Oxidation,” *ACS Sustainable Chemistry and Engineering*, doi: https://doi.org/10.1021/acssuschemeng.1c05728.
A. Razali, et al., “Effect of corrugating the cold orifice of a vortex tube on its flow and energy separation features,” *International Journal of Fluid Mechanics Research*, doi: https://doi.org/10.1615/InterJFluidMechRes.2021038749.
M. Amidu, et al., “Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors,” *Nuclear Engineering and Design*, doi: https://doi.org/10.1016/j.nucengdes.2021.111107.
M. Amidu, “Toward Mechanistic Wall Heat Flux Partitioning Model for Fully Developed Nucleate Boiling,” *Journal of Heat Transfer*, doi: https://doi.org/10.1115/1.4052198.
C. Verma, et al., “N-heterocycle compounds as aqueous phase corrosion inhibitors: A robust, effective and economic substitute,” *Journal of Molecular Liquids*, doi: https://doi.org/10.1016/j.molliq.2021.117211.

Year 2020

O. Al-Yahia, et al., “Numerical analysis of single-phase thermal hydraulic parameters along nanostructured coating film,” *International Conference on Nuclear Engineering, Proceedings, ICONE*, doi: https://doi.org/10.1115/ICONE2020-16316.
M. Amidu and Y. Addad, “Numerical prediction of the reactor pressure vessel melting under IVR-ERVC conditions,” *ATH 2020 – International Topical Meeting on Advances in Thermal Hydraulics*, pp. 582–590, 2020.
O. Al-Yahia, et al., “Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution,” *Nuclear Engineering and Technology*, doi: https://doi.org/10.1016/j.net.2020.05.025.
J. Alsuwaidi, et al., “The risk analysis of the electrical Cross-tie for extended Station Blackout in Multi-Unit site,” *Annals of Nuclear Energy*, doi: https://doi.org/10.1016/j.anucene.2020.107660.
Adam D. Williams, Alexander A. Solodov, Amir H. Mohagheghi, Philip A. Beeley, Saeed Alameri, “The Gulf Nuclear Energy Infrastructure Institute: A Multidisciplinary Educational Approach for Integrated Nuclear Energy Safety, Security and Safeguards in the Middle East”, Journal of Nuclear Materials Management, 2020 Volume XLVIII, No. 1, 4-21.
Amidu M.A., Addad Y., Riahi M.K., “A hybrid multiphase flow model for the prediction of both low and high void fraction nucleate boiling regimes”, Applied Thermal Engineering, https://doi.org/10.1016/j.applthermaleng.2020.115625
Amidu M.A., Addad Y., “An enhanced model for the prediction of slug flow boiling heat transfer on a downward-facing heated wall”, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2020.107596
Moon J., Jeong Y.H., Addad Y., “Design of air-cooled waste heat removal system with string type direct contact heat exchanger and investigation of oil film instability”, Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2019.10.010
Alameri S.A., King J.C., Alkaabi A.K., Addad Y., “Prismatic-core advanced high temperature reactor and thermal energy storage coupled system – A preliminary design”, Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2019.07.028
Kim J.H., Alameri S.A., “Harmonizing nuclear and renewable energy: Case studies”, International Journal of Energy Research, https://doi.org/10.1002/er.4987
Lee M., Lee D., Ko E., Park K., Kim J., Ko K., Sharma M., Cho G., “A Pulse Pileup Correction Method for High Dose Gamma Spectroscopy”, Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2019.12.003
Ho Joon Yoon , Waleed Al Naqbi, Omar Al Yaihi , Daeseong Jo, ” Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data”, Nuclear Engineering and Technology, Feb 2020, https://doi.org/10.1016/j.net.2020.02.007
In Seop Jeon, Ho Joon Yoon, Hyun Gook Kang,” Feasibility estimation of new mitigation system through causal inference analysis with functional model’, Annals of Nuclear Energy, Volume 137, March 2020, 107087. https://doi.org/10.1016/j.anucene.2019.107087

Year 2019

Alrwashdeh M., Alameri S.A., “Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor”, AIP Advances, https://doi.org/10.1063/1.5115807
Amidu M.A., Addad Y., “Bubble-induced enhancement of single-phase liquid forced convection heat transfer during subcooled nucleate flow boiling”, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2019.06.001
Al-Nuaimi A., Alameri S.A., Alkaabi A.K., Shimazu Y., “New monitoring procedure of axial xenon oscillation in large pressurized water reactors”, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2018.12.026
Alrwashdeh M., Alameri S.A., “Evaluation review of the 250Cf neutron cross section”, Applied Radiation and Isotopes, https://doi.org/10.1016/j.apradiso.2019.108869
Mohamed S., Shatilla Y., Zhang T., “CFD-based design and simulation of hydrocarbon ejector for cooling”, Energy, https://doi.org/10.1016/j.energy.2018.10.057
Kim S.G., Addad Y., Liu M., Lee J.I., Lee Y., “Computational investigation into heat transfer coefficients of randomly packed pebbles in flowing FLiBe”, International Journal of Heat and Mass Transfer, https://doi.org/10.1016/j.ijheatmasstransfer.2019.118769
Al-Yahia O.S., Yoon H.J., Jo D., “Bubble dynamic parameters during subcooled flow boiling under uniform and non-uniform transverse heat distribution”, International Journal of Heat and Mass Transfer, https://doi.org/10.1016/j.ijheatmasstransfer.2019.118508
You B.-H., Jeong Y.H., Addad Y., “Assessment of advanced RANS models ability to predict a turbulent swept liquid metal flow over a wire in a channel”, Nuclear Engineering and Design, https://doi.org/10.1016/j.nucengdes.2019.110206
Remache A., Addad Y., Sabeur-Bendehina A., Ouadha A., “Thermal design optimization of passive cooling capability in a dry-storage system by adding wall undulations or semi-circular fins”, Nuclear Eng. and Design, https://doi.org/10.1016/j.nucengdes.2019.03.028
Abutayeh M., Addad Y., Abu-Nada E., Alazzam A., “Doping solar field heat transfer fluid with nanoparticles”, of Solar Energy Eng., https://doi.org/10.1115/1.4041157
Kim J.H., Song M.M., Alameri S.A., “Emerging areas of nuclear power applications”, Nuclear Engineering and Design, https://doi.org/10.1016/j.nucengdes.2019.110183
Kim D.Y., NO H.C., Yoon H.J., Lim S.G., “Thermal-hydraulic study of air-cooled passive decay heat removal system for APR+ under extended station blackout”, Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2018.09.006
Alrwashdeh, M., Alameri, S.A., Alkaabi, A.K., “Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method”, Nuclear Science and Eng., https://doi.org/10.1080/00295639.2019.1672511
Alkaabi, A.K., King, J.C., “Benchmarking COMSOL multiphysics single-subchannel thermal hydraulic analysis of a TRIGA reactor with RELAP5 results and experimental Data”, Science and Technology of Nuclear Installations, https://doi.org/10.1155/2019/4375782
Chen J., Nurrochman A., Hong J.-D., Kim T. S., Yi Y., “Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment”, Nuclear Eng. and Technology, https://doi.org/10.1016/j.net.2018.10.007
Takahashi S., Kawashima S., Hidaka A., Tanaka S., Takahashi T., “Estimation of the Release Time of Radio-Tellurium During the Fukushima Daiichi Nuclear Power Plant Accident and Its Relationship to Individual Plant Events”, Nuclear Technology, https://doi.org/10.1080/00295450.2018.1521186
Hidaka A., “Formation mechanisms of insoluble Cs particles observed in Kanto district four days after Fukushima Daiichi NPP accident”, Journal of Nuclear Science and Technology, https://doi.org/10.1080/00223131.2019.1583611
Park K., Kim J., Lim K., Kim J., Chang H., Kim H., Sharma M., Cho G., “Ambient Dose Equivalent Measurement with a CsI(Tl) Based Electronic Personal Dosimeter”, Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2019.06.017

Year 2018

Al Hanaee S., Yi Y., Schiffer A., “Ultimate pressure capacity of nuclear reactor containment buildings under unaged and aged conditions”, Nuclear Engineering and Design, https://doi.org/10.1016/j.nucengdes.2018.05.017
Baghdad M., Ouadha A., Addad Y., “Effects of kinetic energy and conductive solid walls on the flow and energy separation within a vortex tube”, International Journal of Ambient Energy, https://doi.org/10.1080/01430750.2018.1550013

Year 2017

Choi M.K., Lee S.M., Ha J.S., Seong P.H., “Development of an EEG-based Workload Measurement Method in Nuclear Power Plants”, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2017.08.032
Byon Y.-J., Ha J.S., Cho C.-S., Kim T.-Y., Yeun C.Y., “Real-Time Transportation Mode Identification Using Artificial Neural Networks Enhanced with Mode Availability Layers: A Case Study in Dubai”, Applied Sciences, https://doi.org/10.3390/app7090923
Al Mehrzi A., Yi Y., Cho P.Y., Al Saadi S., Lee J.S., Choi D.S., “Deliquescence of NaCl and Atmospheric Corrosion of 316L Stainless Steel”, Advanced Materials Research, https://doi.org/10.4028/www.scientific.net/AMR.1142.8
Addad, Y., Abutayeh, M., Abu-Nada, E., “Effects of Nanofluids on the Performance of a PCM-Based Thermal Energy Storage System”, Journal of Energy Engineering, https://doi.org/10.1061/(ASCE)EY.1943-7897.0000433
Lee W.W., Bae S.J., Jung Y.H., Yoon H.J., Jeong Y.H., Lee J.I., “Improving power and desalination capabilities of a large nuclear power plant with supercritical CO2 power technology”, Desalination, https://doi.org/10.1016/j.desal.2017.01.013
Park Y.J., Kim J.W., Ali G., Kim H.J., Addad Y., Cho S.O., “Fabrication of Uniform Nanoporous Oxide Layers on Long Cylindrical Zircaloy Tubes by Anodization Using Multi-Counter Electrodes”, Nanoscale Research Letters, https://doi.org/10.1186/s11671-016-1774-1
Solodov A., Williams A., Al Hanaei S., Goddard B., “Analyzing the threat of unmanned aerial vehicles (UAV) to nuclear facilities”, Security Journal, https://doi.org/10.1057/s41284-017-0102-5

UAE Ministry of Energy and Industry Launches Emirates Nuclear Technology Center at Khalifa University’s Sas Al Nakhl Campus in Abu Dhabi

The new center will support research, innovation and capacity building in the UAE’s peaceful nuclear energy industry
A Memorandum of Understanding has been signed by UAE’s MoEI, and the Korea’s MoFA to cooperate in research projects

The UAE Ministry of Energy and Industry opened the Emirates Nuclear Technology Center, at Khalifa University’s Sas Al Nakhl Campus in Abu Dhabi, UAE, to support the long-term sustainability of the UAE Peaceful Nuclear Energy Program by creating a dedicated innovation hub for peaceful nuclear technologies.

A Memorandum of Understanding (MoU) was exchanged by His Excellency Suhail Bin Mohammed Faraj Faris Al Mazrouei, UAE Minister of Energy and Industry, and His Excellency Lee Taeho, Second Vice Minister of Foreign Affairs, Republic of Korea, during the opening ceremony, attended by His Excellency Engineer Mohamed Al Hammadi, Chief Executive Officer of ENEC, Christer Viktorsson Director General of the Federal Authority of Nuclear Regulation (FANR), Dr. Arif Sultan Al Hammadi Executive Vice President of Khalifa University, and senior officials from all five entities.

The MoU between the UAE MoEI and the Ministry of Science, and Information and Communications Technology of Korea, under the UAE-Korea Consultation Committee on Nuclear Technology, outlines the framework of cooperation on research projects between the center’s relevant partners.

The Emirates Nuclear Technology Center will engage in research projects designed and approved by ENEC and FANR, and will be conducted by students, academics and researchers from Khalifa University. The Center’s initial research projects will focus on three areas – nuclear safety and systems, nuclear materials science and chemistry, and radiation safety in the environment.

Through the MoU, the ENTC will benefit from sharing of knowledge and expertise from the Korean nuclear energy industry, which has been operating for over 40 years, along with experience in developing nuclear research reactors.

“It is my pleasure to launch the Emirates Nuclear Technology Centre in Abu Dhabi, which is an outcome of our collaborative approach with our South Korean government counterparts and all UAE nuclear stakeholders, who are working to further Nuclear Science & Technology Research and Development. Investing in research and innovation are prerequisites for the long-term success of the UAE’s peaceful nuclear energy industry. It will further position the UAE as an international role model for the development of a peaceful nuclear energy program by building UAE National capabilities and conducting industry-leading research on radiation safety and nuclear energy technologies,” said His Excellency Suhail Al Mazrouei.

“Within the frame of the High-Level Consultation on Nuclear Cooperation, we and our UAE partner are expanding areas of cooperation in the Barakah Nuclear Energy Plant construction and operations, new nuclear energy project in third countries, nuclear R&D, and safety regulations. I believe that the MoU on nuclear energy and R&D cooperation will serve as a catalyst that will further accelerate our bilateral nuclear energy cooperation”, said His Excellency Lee Taeho,.

H.E. Eng. Mohamed Al Hammadi, CEO of ENEC, said: “We are delighted to be part of this initiative to establish the Emirates Nuclear Technology Center. As the UAE’s emerging peaceful nuclear energy industry continues to grow and develop, collaboration and cooperation between academia and industry will allow us to ensure the long-term sustainability of the UAE Peaceful Nuclear Energy Program, as well as enhancing our global competitiveness and high standards of safety. Through its projects and research the Center will provide talented UAE Nationals with the opportunity to work alongside international experts in conducting cutting-edge research, thereby developing their skills and capabilities within the field of peaceful nuclear energy.”

Dr Arif Sultan Al Hammadi, Executive Vice-President, Khalifa University of Science and Technology, said: “We are delighted to join the official launch of the Emirates Nuclear Technology Center (ENTC), hosted on our campus, in collaboration with our stakeholders including our partners ENEC and FANR. The ENTC reflects another strong commitment from Khalifa University to contribute to enhancing the UAE’s nuclear technology research capability and support our key stakeholder’s goals for the delivery of safe, clean and efficient nuclear technology to meet the UAE 2030 vision. The center will significantly optimize the multidisciplinary capabilities through Khalifa University’s diverse community of faculty and researchers to meet the national objectives.”

“We are delighted to join our national and international stakeholders in launching the Emirates Nuclear Technology Centre. Investing in research and innovation in nuclear technologies is indispensable to ensure the sustainability of the nuclear program. We will work closely with our partners to identify priority areas, focus on strategic nuclear sector research, ensure continuity of projects and provide support to national and international initiatives in line with FANR’s R & D Policy, which was launched in 2017. FANR will support the mandate of the new center by utilizing its Research and Development Program. FANR’s Research and Development Program aims to develop and attract Emiratis by providing opportunities for postgraduate education and research in the nuclear field. It also aims to ensure sound technical basis for all regulatory activities, mitigate risks related to safety, security and safeguards in the UAE nuclear sector,” said Christer Viktorsson, Director-General of the Federal Authority for Nuclear Regulation (FANR) in the UAE.

The establishment of the Emirates Nuclear Technology Center will cement the UAE’s position as an international role model for the development of a new peaceful nuclear energy projects around the globe. Innovation and continuous development are essential to the sustainability and long-term success of the UAE’s peaceful nuclear energy industry, as well as the UAE’s ongoing transition to a knowledge-based economy and society.

The MoU comes at a pivotal time for ENEC, with the 4 Units of Barakah Nuclear Energy Plant more than 93% complete. Unit 4 is over 82% complete, Unit 3 is more than 91% and Unit 2 is more than 95%. Unit 1 construction has been completed and is currently undergoing operational readiness preparations pending regulatory approval and receipt of the Operating License for Unit 1 from FANR, anticipated in early 2020.

After the launch of ENTC and the MoU signing, His Excellency Suhail Al Mazroui, His Excellency Lee Taeho and members of the official delegation from Korea, ENEC, and FANR along with Khalifa University senior management team, faculty members and researchers toured the research facility.

Later, delegation members from the two countries attended the second meeting of the ‘UAE-Korea high-level consultations on nuclear cooperation’.

Modeling of Radionuclides Dispersion in the UAE Environment (MORAD) research project (7 million AED), PI: Dr. Yacine Addad, CO-I: Diana Francis.

Dr. Yacine Addad, Associate Professor of Nuclear Engineering and Theme-1 lead of the Emirates Nuclear Technology Center (ENTC), is leading collaborative research project with IRSN, France and FANR, UAE. The project is being funded by the Federal Authority for the Nuclear Regulation, UAE.

The aim of this research program is to enhance the capabilities of the UAE to simulate radionuclides dispersion in marine, atmospheric and continental environments taking account for regional and local features. Since UAE has started the nuclear program by constructing four nuclear power plants, UAE is putting intensive efforts in increasing human capability on nuclear safety. This objective is in-line with the Abu Dhabi Economic Vision 2030 as it serves the purpose of the development of a highly-skilled, science-oriented, workforce of UAE Nationals, and it lays the foundations for research & development in the field of nuclear energy safe usage, which not only supports the Plan’s goal of diversification of the Emirate’s economy but also minimizes the impact of this newly adopted sustainable energy source on the natural environment.

ENTC won high value MOE grant: Collaborative Research Program Grant 2019

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.

Recently, a KU team lead by Dr. Saeed Alameri and 6 more faculty members, along with 3 external collaborators from MIT, KAIST and University of Manchester won a high value grant of the Ministry of Education Collaborative Research Program Grant 2019 in which just 4 awards were selected out of 238 proposals in the whole country. The topic is about (Evaluation of Using Accident Tolerant Fuel Concepts in APR1400) with a total amount of almost AED 7M. The following are the main objectives of this research:

Evaluate the impact of using ATFs on the safety of APR1400;
Evaluate the performance of ATFs in APR1400;
Determine the allowable ranges of reactor critical parameter values; and
Assessment studies on the suitability of using ATFs in APR1400.

Thermal hydraulic studies on Design Basis Accident and Design extension conditions of APR1400 via OECD-ATLAS experimental program (2 million AED), PI: Assist. Prof. Ho Joon Yoon

ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) facility has been constructed to develop new safety concepts and verify their performance in APR1400. Valuable large-scale integral effect test (IET) data were produced and effectively utilized for domestic standard program (DSP) and International standard program (ISP). ATLAS has been recognized as one of the important IET facilities worldwide since the ISP-50 was successfully completed in 2011, where 14 organizations from 11 OECD countries participated.

OECD/NEA ATLAS project has been initiated in 2014 for further international cooperation to deal with common safety issues relevant to PWR, and proposed five topics related to beyond design basis accidents. UAE is participating in the project to increase local human capability on safety analysis. To this end, FANR and Khalifa University are planning to cooperate in the UAE participation to the ATLAS project, which will consist in conducting numerical simulations, using RELAP5; the blind pre-test and post-test simulations. The blind pre-tests rely on only specification of experiment given by the operating agency. The post-test simulation can be performed after acquiring experiment data from the operating agency.

At the start of the project, the Operating Agency (OA), KAERI, has provided the steady-state input deck of RELAP5/MOD3 for ATLAS facility to all participants. Then each participating agency has to generate its own transient input in accordance with proposed experiment scenarios. Although this might seem a trivial exercise at first glance, the generation of transient input is strongly dependant on experience and know-how level of the user groups. The given steady-state inputs also need to be modified and some component have to be remodelled to cope with the newly proposed scenario. For this reason, previous similar projects revealed that each participating agency come up with different results even though they have been using the same safety analysis code.

Preparation of input, running simulation, debugging process, interpretation of results and all lessons learned will be consolidated as a training material for increasing local human capability on safety analysis.

Additionally, at least one local component will be selected from each proposed scenario to investigate the detailed thermal hydraulic phenomena using the computational fluid dynamics (CFD) approach. Simulation results from RELAP5 will then be compared with both; the CFD predictions and the experimental data from ATLAS facility.

Advanced Investigation of Condensation Phenomena: Experimental Validation and Multiscale , Modelling for Advancing Power Plant Safety

This research examines condensation heat transfer in nuclear passive cooling systems, highlighting thermal resistance caused by non condensable gases. It integrates experiments, TRACE simulations, and machine learning to improve understanding and optimize reactor safety and performance.

Charging and transport dynamics of atmospheric radioactive aerosols in the UAE environment

Dispersion models predict the spread and deposition of natural or anthropogenic radionuclides in the atmosphere.This project systematically examines the key physical processes influencing transport, deposition, charge evolution, decay, and coagulation of radioactive aerosols focusing on the UAE’s hot, arid climate and dust outbreaks.

Dynamic Assessment and Optimization of Thermal Energy Storage Integration with Nuclear Power Plants Using Machine Learning and Computational Fluid Dynamics

Faizan, I Afgan | Accepted

“Dynamic Assessment and Optimization of Thermal Energy Storage Integration with Nuclear Power Plants Using Machine Learning and Computational Fluid Dynamics” Applied Energy

Influence of variable gravity on the phase change material for enclosed vertical channels with helical fins

Faizan, AK Alkaabi, I Afgan | https://doi.org/10.1016/j.est.2024.112577

“Influence of variable gravity on the phase change material for enclosed vertical channels with helical fins” Applied Thermal Engineering

Impactful research outputs, graphical abstracts, and links to publications:

Faizan, AK Alkaabi, B Nie, I Afgan | https://doi.org/10.1016/j.ijthermalsci.2020.106793

“Thermal energy storage integration with nuclear power: A critical review” Journal of Energy Storage

Materials technology and structural integrity in uaes’s nuclear power plants

Theme 2 focuses on Improving nuclear plant safety and durability through advanced materials. Key efforts include corrosion-resistant coatings, concrete degradation mitigation, ATF cladding evaluation, and HDPE pipe welding optimization.
These initiatives enhance the reliability of nuclear infrastructure.

Impact of replacing Zircaloy cladding with accident tolerant silicon carbide cladding on corium characteristics

The findings from this study indicate that

The adoption of silicon carbide cladding leads to significantly reduced concrete ablation during the interaction with molten corium.

Furthermore a crucial aspect lies in the utilization of silicon carbide-based cladding, which effectively contributes to notable reduction in the generation of
- Highly combustible gases such as H2 and CO,
- Concurrently resulting in a upsurge in the production of inert CO2 gas.

Experimental study of boiling heat transfer of inclined downward facing heated curved wall under low flow and pressure conditions

Curvature markedly affects flow boiling heat transfer on downward-facing surfaces, highlighting the need for to develop predictive models and optimize geometrics for enhanced thermal performance in reactor safety applications.

Protecting Nuclear Installations Against Natural Hazards and Climate Change Effects.

We recently hosted a seminar at the Emirates Nuclear Technology Center (ENTC) with Dr. Hervé, titled “Protecting Nuclear Installations Against Natural Hazards and Climate Change Effects.” The session provided valuable insights into the challenges and solutions for safeguarding nuclear installations in the face of natural hazards and climate change.

Nuclear Engineering Educational Programs and R&D Activities at Khalifa University

We are delighted to have hosted the ANS group from the American Nuclear Society at Khalifa University. During their visit, Dr. Yacine gave a brief presentation about the Nuclear Engineering Educational Programs and R&D Activities at Khalifa University, followed by a tour of our advanced labs. The tour was supported by our lab engineers, who provided detailed insights into the facilities and ongoing research. It was a wonderful opportunity to showcase our work and engage with the group.

MSc students’ activities on the integrity of reactor containment buildings in Barakah nuclear power plants

Reactor containment buldings (RCBs) as the last barrier to the release of radioactive materials play a critical role in the nuclear power plants (NPPs). Thus, the integrity of RCBs has been studied as one of the projects in the ENTC.

Several MSc students in Nuclear Engineering have participated in the project and after graduation they are actively working on the safety and security areas of NPPs at FANR and ENC/NAWAH. Sara Al Hanaee, one of the MSc graduates, completed her MSc Thesis titled ‘Effect of aging on ultimate pressure capacity of nuclear reactor containment building, which was published in a journal named ‘Nuclear Engineering and Design’. She was one of the three winners of the competition at the 10th anniversary of the World Institute for Nuclear Security (WINS) operation in 2018. Also, while working at FANR, she was a winner of FANR Annual Award “Exceptional Employee Award” in 2019.

ENTC fulfilling its educational mission: A national MSc student presented her research at Program Review meeting and international conference

Nourah Alyammahi is a full-time MSc student in nuclear engineering under the supervision of Assist. Prof. Ho Joon Yoon. She is also a FANR nuclear safety assessment engineer, was selected to participate in the ATLAS-2 Project. Her MSc thesis is to conduct the numerical analysis using one of the thermal hydraulic safety analysis code, RELAP 5, whilst conducting experiments and tests developed by the Korean Atomic Energy Research Institute. She participated in every test and experiment over the last two years and put UAE on the global stage regarding thermal hydraulic safety analysis by presenting Five of her research findings at ATLAS Project Review Meetings. On each occasion, the Emirati demonstrated vast improvements in her skills and knowledge, and in her ability to convey technical analysis to a highly-skilled and knowledgeable audience. In May 2019 She also delivered a paper on RELAP 5 simulation of intermediate break loss of coolant accident at the International Congress on Advances in Nuclear Power (ICAPP) in France.