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Ouadie Kabach

Observed names: KABACH Ouadie, Kabach Ouadie, O. Kabach, Ouadie KABACH
ORCID: 0000-0002-3978-7555
Observed ORCID: 0000-0002-3978-7555
OpenAlex ID: A5017340930
Assessment of radiation shielding properties for some concrete mixtures against photon and neutron radiations
2025 · Brahim EL Azzaoui, Ouadie Kabach, et al. · Nuclear Analysis · 33
The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2
2021 · Ouadie Kabach, Abdelouahed Chetaine, et al. · Nuclear Engineering and Design · 23
Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis
2023 · Oussama El Kheiri, Ouadie Kabach, et al. · Progress in Nuclear Energy · 21
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
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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 burnable absorbers: Assessing PaO2 and NpO2 coatings for improved safety in (Th-233U-235U)O2 fuel assemblies
2024 · Ouadie Kabach, El Mahjoub Chakir, et al. · Nuclear Engineering and Design · 16
An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
2021 · Ouadie Kabach, Abdelouahed Chetaine, et al. · Nuclear Engineering and Technology · 16
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Neutronic investigation of the thorium-based mixed-oxide as an alternative fuel in the TRIGA Mark-II research reactor – Part I: A beginning of life calculations
2019 · Ouadie Kabach, Abdelouahed Chetaine, et al. · Annals of Nuclear Energy · 16
Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX
2019 · Ouadie Kabach, Abdelouahed Chetaine, et al. · Applied Radiation and Isotopes · 16
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
Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016
2017 · Kabach Ouadie, Chetaine Abdelouahed, et al. · Nuclear Engineering and Technology · 10
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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
Neutron beam characterization for the Moroccan TRIGA Mark II reactor
2021 · Hamid Amsil, Abdelhamid Jalil, et al. · Journal of Radioanalytical and Nuclear Chemistry · 8
Calculations of the principal neutronic characteristics of a hypothetical VVER assembly with minor actinides incorporated into PuO2-ThO2 fuel in a duplex configuration
2024 · Achraf Radi, Ouadie Kabach, et al. · Nuclear Energy and Technology · 7
Revolutionizing LWR SMR reactors: exploring the potential of (Th- 233 U- 235 U)O 2 fuel through a parametric study
2023 · Mohamed Lkouz, Ouadie Kabach, et al. · Energy Sources Part A Recovery Utilization and Environmental Effects · 7
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
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Integrated neutronic evaluation of HTR-10 at various accident tolerant fuel types based on (Th-233U-TRU)
2025 · Shlash A. Luhaib, Ouadie Kabach, et al. · Annals of Nuclear Energy · 6
Radiation Dose Calculation Analysis During The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results
2024 · B. El Azzaoui, O. Kabach, et al. · Atom Indonesia · 6
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The Moroccan PGAA System: Design, Installation, and Challenges.
2023 · hamid AMSIL, Abdessamad DIDI, et al. · Arab Journal of Nuclear Sciences and Applications · 6
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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
A comprehensive assessment of neutronic and thermal–hydraulic behavior of some advanced accident-tolerant fuels in solid and dual-cooled annular PWR assemblies
2026 · Ouadie Kabach, Sinem Uzun, et al. · Annals of Nuclear Energy · 5
Research reactors: Global perspectives and insights into Saudi Arabia’s advancements and future prospects
2025 · Afaque Shams, Ouadie Kabach, et al. · Annals of Nuclear Energy · 5
Neutronic analysis of different sandwich cladding material options for (Th-233U-235U)O2 annular fuel in advanced PWR assembly
2024 · Taoufiq Bouassa, Ouadie Kabach, et al. · Interactions · 5
Works count: 56
Citation count: 327
H-index: 11
I10-index: 13
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