
Nuclear engineer with a Ph.D. and 5+ years of combined industry and research experience in reactor core design, Monte Carlo neutron transport, and safety analysis. Designed and authored licensing-basis analyses for a commercial micro-reactor dry critical experiment. Developed novel computational methods for reactor transient simulation published in leading international journals and conferences. Fluent in Serpent 2, OpenMC, and Python; experienced with HPC environments and regulatory-grade documentation.
§ ANS 2021 Virtual Conference, F. Abdullatif, “O-SRS: A Refueling and Shuffling Toolkit for Serpent Core Neutronics Analysis".
§ PHYSOR 2022 International Conference, Pittsburgh, F. Abdullatif "Acceleration of Source Convergence in Monte Carlo Criticality Calculation with CMFD Schemes”.
§ ANS 2023 Annual Conference, Indianapolis, F. Abdullatif " A Multilevel Quasi-Static Kinetics Module for Monte Carlo Simulations”.
§ PHYSOR 2024 International Conference, San Francisco, F. Abdullatif, “Implementation and Assessment of the Crank-Nicolson Method for the Monte Carlo Multilevel Kinetics Module".