Get started
Author

Fadi El Banni

ORCID: 0000-0002-0170-6887
Observed ORCID: 0000-0002-0170-6887
OpenAlex ID: A5059463928
A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor
2021 · Ouadie Kabach, Abdelouahed Chetaine, et al. · International Journal of Energy Research · 21
PDF
Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis
2022 · Zohair Benrhnia, Abdelouahed Chetaine, et al. · International Journal of Energy Research · 19
Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly
2023 · Taoufiq Bouassa, Ouadie Kabach, et al. · Nuclear Engineering and Design · 17
Innovative thorium-based fuel assemblies for LW-SMR: In-depth assembly-level neutronic analysis and safety considerations in solid and annular configurations
2025 · Hanan Rifai, Ouadie Kabach, et al. · Nuclear Engineering and Design · 12
Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study
2024 · Fadi El Banni, Bogbe L. H. Gogon, et al. · Nuclear Energy and Technology · 10
Neutronic investigation of a VVER-1200 (Th-233U)O2 fuel assembly with protactinium oxide as a burnable absorber coated on the outer surface of the fuel rods
2022 · Fadi El Banni, Ouadie Kabach, et al. · Energy Sources Part A Recovery Utilization and Environmental Effects · 9
Thermal-hydraulic investigation of novel thorium-uranium fuel mixtures in advanced SMR assembly configurations
2025 · Sinem Uzun, Yasin Genç, et al. · Nuclear Energy and Technology · 6
PDF
Neutronic feasibility study of ( Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor
2021 · Fadi El Banni, Ouadie Kabach, et al. · Journal of King Saud University - Science · 6
Coupled Neutronic and Thermal-Hydraulic Analysis of Inner Moderator Radius Effects in Dual-Cooled Annular UO 2 and Thorium-Based Fuels for a LW-SMR
2026 · Ouadie Kabach, Hanan Rifai, et al. · Nuclear Science and Engineering
Comparative neutronic analysis and safety-related neutronic considerations of thorium-based fuels under different loading patterns in a Westinghouse-SMR-like core
2026 · Fadi El Banni, Ouadie Kabach, et al. · Nuclear Analysis
Works count: 10
Citation count: 100
H-index: 6
I10-index: 5
Year
Topic
Type