Hossam Abdellatif, Ph.D. profile photo

Hossam Abdellatif, Ph.D.

Assistant Professor, Mechanical and Nuclear Engineering

  • Richmond VA UNITED STATES

Dr. Abdellatif teaches various nuclear engineering courses, conduct research in thermal-hydraulics and contribute to department service.

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Biography

Dr. Hossam Abdellatif joined the Department of Mechanical and Nuclear Engineering at Virginia Commonwealth University in August 2026. He previously served as an Adjunct Assistant Professor in the department, where he taught System Analysis of the Nuclear Fuel Cycle course. Prior to joining VCU, he was a Postdoctoral Fellow at Kansas State University, where he conducted research in advanced reactor thermal-hydraulics and contributed to undergraduate and graduate nuclear engineering education. He also conducted research at Idaho National Laboratory and the University of Pisa on small modular reactors, Generation IV systems, and reactor safety.Dr. Abdellatif received his B.S. in Nuclear Engineering from Alexandria University, his M.Sc. in Nuclear Engineering from the University of Pisa, and his Ph.D. in Nuclear Engineering from the University of Idaho. His research interests include nuclear thermal-hydraulics, reactor safety and accident analysis, natural circulation systems, computational fluid dynamics, and advanced reactor technologies.Among his honors, Dr. Abdellatif received the 2025 Outstanding Graduate Student Research and Creative Activity Award and the 2024 Award for Excellence from the University of Idaho. His additional honors include a research grant and a merit-based scholarship from the University of Pisa, a B.S. Graduation Project Award from Alexandria University, and research funding from Egypt’s Academy of Scientific Research and Technology.

Industry Expertise

Nuclear
Energy
Safety

Areas of Expertise

Nuclear reactor thermal-hydraulics
Nuclear Engineering
Computational Fluid Dynamics
Natural-circulation systems
Validation and Verification
Nuclear Reactor Safety

Education

University of Idaho

Ph.D.

Nuclear Engineering

2025

University of Pisa

M.Sc.

Nuclear Engineering

2021

Alexandria University

B.Sc.

Nuclear Engineering

2013

Courses

EGMN 610 - Topics in Nuclear Engineering

Fall 2026

EGMN 574 - Nuclear Safeguards, security and Nonproliferation

Fall 2026

EGMN 530 - System Analysis of Nuclear Fuel Cycle course

Spring 2026

Selected Articles

Similarity Analysis of High-Prandtl Surrogate Fluids for Thermal-Hydraulic Studies of Molten Salt Reactors

Annals of Nuclear Energy

Hossam H. Abdellatif, David Arcilesi, Richard Christensen, Arsen Iskhakov

2025-08-06

Molten salt reactors (MSRs) require high-temperature testing of corrosive fluids like FLiBe and FLiNaK, complicating integral and separate effect experiments. To overcome these limitations, this study employs a similarity-based methodology, grounded in the hierarchical two-tier scaling (H2TS) framework to investigate the performance of Therminol-66, DOWTHERM A, and DOWTHERM RP as low-temperature, high-Prandtl-number surrogates for fluoride salts. We first match each simulant’s Prandtl number to its corresponding salt at the reactor’s mean operating temperature, then derive all relevant non-dimensional groups under forced and natural circulation. Applying this to three MSR designs, KP-FHR, FuSTAR, and FUJI-233Um, yields compact, low-power test loops with zero distortion in all primary groups and negligible Biot-number error. Nusselt-number predictions using standard correlations show that heat transfer is replicated to within 1% over the target Re-Pr range. These results establish a practical, safe, and scalable pathway for high-fidelity thermal-hydraulic experiments supporting future MSR developments.

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Flow Instabilities in boiling channels and their suppression methodologies—A review

Nuclear Engineering and Design

Hossam H Abdellatif, Walter Ambrosini, David Arcilesi, Palash K Bhowmik, Piyush Sabharwall

2024-03-19

Small modular reactors (SMRs) are gaining significant attention as a promising solution for clean and sustainable nuclear-power generation. However, the operation of SMRs is subject to various challenges, including two-phase flow instabilities. Flow instability has the potential to trigger flow-induced vibration and cyclic fluctuations in local thermal stress. These instabilities frequently manifest because of the complex interplay among a multitude of factors, encompassing thermal-hydraulic conditions, the geometric configuration of the steam generator, and operational parameters. These conditions could subsequently lead to premature critical heat flux, equipment malfunctions, and other safety concerns. The endeavor to address steam-generator flow instabilities is of utmost importance in augmenting the sustainability and efficiency of contemporary energy production. This study offers a comprehensive review of instabilities in two-phase flow, with a particular focus on the influential factors impacting the stability of flow boiling. Furthermore, it delves into the processes of identifying, characterizing, and ameliorating these instabilities, emphasizing pivotal findings, methodologies employed, and avenues for prospective research. The primary parameters of concern encompass the efficient transfer of thermal energy, the optimization of mass-flow rates, and the establishment of favorable boundary conditions, all in the context of steam generator design to alleviate instability for water-cooled SMRs. These discernments bear substantial ramifications for enhancing reactor performance and ensuring operational safety.

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Preliminary experimental validation of single-phase natural circulation loop based on RELAP5-3D code: Part I

Journal of Nuclear Engineering

Hossam H Abdellatif, Joshua Young, David Arcilesi, Richard Christensen

2025-09-19

The molten salt reactor (MSR) is a prominent Generation IV nuclear reactor concept that offers substantial advantages over conventional solid-fueled systems, including enhanced fuel utilization, inherent passive safety features, and significant reductions in long-lived radioactive waste. Central to its safety strategy is a reliance on natural circulation (NC) mechanisms, which eliminate the need for active pumping systems and enhance system reliability during normal and off-normal conditions. However, the challenges associated with molten salts, such as their high melting points, corrosivity, and material compatibility issues, render experimental investigations inherently complex and demanding. Therefore, the use of high-Pr-number surrogate fluids represents a practical alternative for studying molten salt behavior under safer and more accessible experimental conditions. In this study, a single-phase natural circulation loop setup at the University of Idaho’s Thermal–Hydraulics Laboratory was employed to investigate NC behavior under various operating conditions. The RELAP5-3D code was initially validated against water-based experiments before employing Therminol-66, a high-Prandtl-number surrogate for molten salts, in the natural circulation loop for the first time. The RELAP5-3D results demonstrated good agreement with both steady-state and transient experimental results, thereby confirming the code’s ability to model NC behavior in a single-phase flow regime. The results also highlighted certain experimental limitations that should be addressed to enhance the NC loop’s performance. These include increasing the insulation thickness to reduce heat losses, incorporating a dedicated mass flow measurement device for improved accuracy, and replacing the current heater with a higher-capacity unit to enable testing at elevated power levels. By identifying and addressing the main causes of these limitations and uncertainties during water-based experiments, targeted improvements can be implemented in both the RELAP5 model and the experimental setup, thereby ensuring that tests using a surrogate fluid for MSR analyses are conducted with higher accuracy and minimal uncertainty.

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