KABACH Ouadie
Email : ouadie.kabach@uit.ac.ma
Institution : Faculty of Sciences
Laboratory : Physics of Materials and Subatomic Physics
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📚 Scopus Publications — Total : 43
| Title | Year | 🔗 View |
|---|---|---|
| Integrated neutronic evaluation of HTR-10 at various accident tolerant fuel types based on (Th-233U-TRU) | 2026 | 🔗 View |
| Evaluation of photon energy shielding and mechanical properties of concrete mixtures based on Tunisian barite: simulation and experimental findings | 2026 | 🔗 View |
| Indoor air quality in primary schools: real-time monitoring and predictive modeling of PM10 in Kenitra, Morocco | 2026 | 🔗 View |
| Research reactors: Global perspectives and insights into Saudi Arabia's advancements and future prospects | 2025 | 🔗 View |
| Assessment of Radiological Dispersal Devices in Densely Populated Areas: Simulation and Emergency Response Planning | 2025 | 🔗 View |
| Innovative thorium-based fuel assemblies for LW-SMR: In-depth assembly-level neutronic analysis and safety considerations in solid and annular configurations | 2025 | 🔗 View |
| Dose distribution comparison using image registration principles | 2025 | 🔗 View |
| Optimizing neutron shielding: A specialised container approach for Disused Sealed Radioactive Sources and orphan neutron emitters | 2025 | 🔗 View |
| Assessment of radiation shielding properties for some concrete mixtures against photon and neutron radiations | 2025 | 🔗 View |
| Preliminary performance evaluation of an LEU+ based dual-cooled duplex UO2-ThO2 fuel for advanced PWR assembly | 2025 | 🔗 View |
| Generating optimal reloading patterns for CNPGS Unit-3 core using multi-objective elitist teaching-learning-based optimizer | 2025 | 🔗 View |
| Thermal-hydraulic investigation of novel thoriumuranium fuel mixtures in advanced SMR assembly configurations | 2025 | 🔗 View |
| Neutronic analysis of different sandwich cladding material options for (Th-233U-235U)O2 annular fuel in advanced PWR assembly | 2024 | 🔗 View |
| Innovative burnable absorbers: Assessing PaO2 and NpO2 coatings for improved safety in (Th-233U-235U)O2 fuel assemblies | 2024 | 🔗 View |
| Calculations of the principal neutronic characteristics of a hypothetical VVER assembly with minor actinides incorporated into PuO2-ThO2 fuel in a duplex configuration | 2024 | 🔗 View |
| Analyzing (Th-233U-235U)O2 fuel performance in various assembly configurations: A comparative neutronic study | 2024 | 🔗 View |
| Assessing the Impact of Meteorological Parameters and Topography on Radioactive Plume Dispersion: A Simulation Study Using the HotSpot Model | 2024 | 🔗 View |
| A Proposed Methodology for Gamma Radiation Activity Correction Using Monte Carlo Simulation | 2024 | 🔗 View |
| Radiation Dose Calculation Analysis During The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results | 2024 | 🔗 View |
| Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly | 2023 | 🔗 View |
| Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis | 2023 | 🔗 View |
| Application of high-thickness integral fuel burnable absorber ZrB2 in a dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactor | 2023 | 🔗 View |
| Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study | 2023 | 🔗 View |
| Enhancing temperature reactivity coefficients in SMR Reactor with (Th-233U-235 U)O2 fuel through PaO2 as a burnable absorber | 2023 | 🔗 View |
| Neutronic and burnup characteristics of potential dual-cooled annular (Th-233U-235U)O2 fuel for the advanced pressurized water reactors: An assembly-level analysis | 2022 | 🔗 View |
| Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor | 2022 | 🔗 View |
| Simulation of LEU and MOX fuels in Russian VVER-1000 reactor with the OpenMC code and recent data libraries | 2022 | 🔗 View |
| Analysis of reactivity control coefficients and the stability of an AP1000 reactor assembly fueled with (Th-233U)O2 using DRAGON code | 2022 | 🔗 View |
| 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 | 🔗 View |
| 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 | 🔗 View |
| A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high-temperature pebble-bed reactor | 2021 | 🔗 View |
| 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 | 🔗 View |
| Neutron beam characterization for the Moroccan TRIGA Mark II reactor | 2021 | 🔗 View |
| Sensitivity analyses of the use of different reflector materials on the main neutronic parameters of the TRIGA Mark-II research reactor | 2021 | 🔗 View |
| 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 | 2020 | 🔗 View |
| Physical protection system, corrective actions, and weaknesses identification based on nuclear security series: The hypothetical atomic research institute (HARI) case | 2020 | 🔗 View |
| 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 | 🔗 View |
| Generation of thermal scattering cross sections for sapphire (Al2O3) and bi crystal filters used in nuclear facilities | 2019 | 🔗 View |
| Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code | 2018 | 🔗 View |
| Processing of the ENDF/B-VIII.0β6 neutron cross-section data library and testing with critical benchmarks, oktavian shielding benchmarks and the doppler reactivity defect benchmarks | 2018 | 🔗 View |
| Evaluation of the IAEA 2D PWR benchmark problem using TRIVAC and openMOC codes | 2018 | 🔗 View |
| 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 | 🔗 View |
| Neutronic analysis of moroccan TRIGA MARK-II research reactor using the DRAGON.V5 and TRIVAC.v5 codes | 2017 | 🔗 View |