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Basma Foad

Observed names: B. Foad, BASMA FOAD
ORCID: 0000-0002-8907-8714
Observed ORCID: 0000-0002-8907-8714
OpenAlex ID: A5025599684
Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient
2022 · Basma Foad, Rabab Elzohery, et al. · Annals of Nuclear Energy · 18
Importance of self-shielding for improving sensitivity coefficients in light water nuclear reactors
2013 · Basma Foad, Toshikazu Takeda · Annals of Nuclear Energy · 14
Efficient uncertainty quantification for PWR during LOCA using unscented transform with singular value decomposition
2020 · Basma Foad, Akio Yamamoto, et al. · Annals of Nuclear Energy · 11
Sensitivity and uncertainty analysis for UO 2 and MOX fueled PWR cells
2014 · Basma Foad, Toshikazu Takeda · Annals of Nuclear Energy · 11
Review of safety improvement on sodium-cooled fast reactors after Fukushima accident
2012 · Toshikazu Takeda, Yoichiro Shimazu, et al. · Natural Science · 11
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Uncertainty and regression analysis of the MSLB accident in PWR based on unscented transformation and low rank approximation
2020 · Basma Foad, Akio Yamamoto, et al. · Annals of Nuclear Energy · 10
Reactivity feedback effect on loss of flow accident in PWR
2018 · Basma Foad, Salwa H. Abdel-Latif, et al. · Nuclear Engineering and Technology · 10
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Applying approximate Bayesian computation to reduce uncertainty in multigroup 235-U cross-sections using ICSBEP experimental data
2023 · Michał Jędrzejczyk, Piotr Kopka, et al. · Nuclear Engineering and Design · 6
Estimation of resonance self-shielding effect in PWR pin cell for different fuel types
2018 · Basma Foad, Riham Refeat · Annals of Nuclear Energy · 6
Development of Calculation Method of Sensitivities for Light Water Reactors
2013 · TOSHIKAZU TAKEDA, BASMA FOAD · Nuclear Engineering and Technology · 6
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Uncertainty & sensitivity analyses for LOCA simulation of PHEBUS experiment FPT-1 using a modified SUNSET code
2020 · B. Foad, M. Hassan, et al. · Annals of Nuclear Energy · 4
Sensitivity and uncertainty analysis of reactivities for UO2 and MOX fueled PWR cells
2015 · Basma Foad, Toshikazu Takeda · AIP conference proceedings · 4
Implementation and testing of unscented transformation and low rank approximation to enhance SCALE code uncertainty calculations
2021 · Basma Foad, David R. Novog · Annals of Nuclear Energy · 3
Uncertainty analysis of minor actinides transmutation in fast reactor cores
2016 · Toshikazu Takeda, Koji Fujimura, et al. · Annals of Nuclear Energy · 3
Sensitivity and uncertainty analyses of reactivities for PWR cells with UO2 and MOX fuels
2015 · Basma Foad, Toshikazu Takeda · Annals of Nuclear Energy · 3
Framework for the correct treatment of model input parameters for Bayesian updating problems in nuclear engineering
2024 · Michał Jędrzejczyk, Piotr Kopka, et al. · Annals of Nuclear Energy · 1
Implementation of the unscented transformation with low rank approximation in uncertainty analysis during large-break loss of coolant accident
2020 · Basma Foad, Akio Yamamoto, et al. · Annals of Nuclear Energy · 1
Development of a Neutronics–Thermal-Hydraulic Coupling Methodology to Support the Safety Analysis of Ghana Research Reactor-1
2025 · Charles Nzoley, Emmanuel K. Boafo, et al. · Nuclear Technology
Convolutional neural network use in fast neutron computed tomography for void fraction measurements
2025 · Qasim Siddiq, Garik G. Patterson, et al. · Nuclear Engineering and Design
Applying Shapley Effect for Sensitivity Analysis During Reactor Transient
2025 · Basma Foad, Rabab Elzohery, et al. · Nuclear Technology
Developing a Machine Learning Benchmark Using Real-Time Data from the PUR-1 Reactor for Nuclear Applications
2024 · William Richards, Zachery Dahm, et al. · Transactions of the American Nuclear Society
Assessment of Resonance Self-shielding Models during Burn-Up Calculations
2021 · Riham Refeat, Basma Foad · Journal of Materials Science and Engineering A
Sensitivity and Uncertainty Analysis of Neuronics Parameters in PWR Cells Using Improved Method
2014 · Basma Foad · Atomic Energy Society of Japan
Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
2010 · B. Foad, H. Mansour, et al. · Kerntechnik
Works count: 24
Citation count: 122
H-index: 7
I10-index: 7
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