Calculations of the principal neutronic characteristics of a hypothetical VVER assembly with minor actinides incorporated into PuO2-ThO2 fuel in a duplex configuration
Radi, Achraf, Kabach, Ouadie, Chakir, El Mahjoub
Published in Nuclear energy and technology (24.10.2024)
Published in Nuclear energy and technology (24.10.2024)
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Journal Article
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
Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid
Published in Nuclear engineering and technology (01.08.2021)
Published in Nuclear engineering and technology (01.08.2021)
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Journal Article
Neutron beam characterization for the Moroccan TRIGA Mark II reactor
Amsil, Hamid, Jalil, Abdelhamid, Kabach, Ouadie, Chahidi, Hassan, Bounouira, Hamid, Elyounoussi, Chafik, Chetaine, Abdelouahed
Published in Journal of radioanalytical and nuclear chemistry (01.03.2021)
Published in Journal of radioanalytical and nuclear chemistry (01.03.2021)
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Journal Article
Physical Protection System, Corrective Actions, and Weaknesses Identification Based on Nuclear Security Series: The Hypothetical Atomic Research Institute (HARI) Case
Ouadie Kabach, Abdelouahed Chetaine, Abdelfettah Benchrif
Published in International journal of nuclear security (01.07.2020)
Published in International journal of nuclear security (01.07.2020)
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Journal Article
Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor
El Banni, Fadi, Kabach, Ouadie, Koua, Aka A., Gogon, Bogbe L.H., Monnehan, Georges A., Benchrif, Abdelfettah, Amsil, Hamid, Chetaine, Abdelouahed
Published in Journal of King Saud University. Science (01.02.2022)
Published in Journal of King Saud University. Science (01.02.2022)
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Journal Article
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
Ouadie, Kabach, Abdelouahed, Chetaine, Abdelhamid, Jalil, Abdelaziz, Darif, Abdelmajid, Saidi
Published in Nuclear engineering and technology (01.12.2017)
Published in Nuclear engineering and technology (01.12.2017)
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Journal Article
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
Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid
Published in Nuclear engineering and technology (2021)
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Published in Nuclear engineering and technology (2021)
Journal Article
Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis
El Kheiri, Oussama, Kabach, Ouadie, Chetaine, Abdelouahed
Published in Progress in nuclear energy (New series) (01.06.2023)
Published in Progress in nuclear energy (New series) (01.06.2023)
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Journal Article
Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study
Lkouz, Mohamed, Kabach, Ouadie, Chetaine, Abdelouahed, Saidi, Abdelmajid, Bouassa, Taoufiq
Published in Energy sources. Part A, Recovery, utilization, and environmental effects (02.10.2023)
Published in Energy sources. Part A, Recovery, utilization, and environmental effects (02.10.2023)
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Journal Article
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
Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid
Published in Nuclear engineering and design (01.12.2021)
Published in Nuclear engineering and design (01.12.2021)
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Journal Article
Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly
Bouassa, Taoufiq, Kabach, Ouadie, Chetaine, Abdelouahed, Benrhnia, Zohair, El Banni, Fadi, Saidi, Abdelmajid
Published in Nuclear engineering and design (01.12.2023)
Published in Nuclear engineering and design (01.12.2023)
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Journal Article
Revolutionizing LWR SMR reactors: exploring the potential of (Th- 233 U- 235 U)O 2 fuel through a parametric study
Lkouz, Mohamed, Kabach, Ouadie, Chetaine, Abdelouahed, Saidi, Abdelmajid, Bouassa, Taoufiq
Published in Energy sources. Part A, Recovery, utilization, and environmental effects (02.10.2023)
Published in Energy sources. Part A, Recovery, utilization, and environmental effects (02.10.2023)
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Journal Article
Generating optimal reloading patterns for CNPGS Unit-3 core using multi-objective elitist teaching-learning-based optimizer
Shaukat, Nadeem, Ali, Amjad, Ahmad, Ammar, Kabach, Ouadie, Al-Athel, Khaled, Shams, Afaque
Published in Progress in nuclear energy (New series) (01.01.2025)
Published in Progress in nuclear energy (New series) (01.01.2025)
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Journal Article
A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor
Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid, El Banni, Fadi
Published in International journal of energy research (01.09.2021)
Published in International journal of energy research (01.09.2021)
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Journal Article
Neutronic and burnup characteristics of potential dual‐cooled annular (Th‐233U‐235U)O2 fuel for the advanced pressurized water reactors: An assembly‐level analysis
Benrhnia, Zohair, Chetaine, Abdelouahed, Kabach, Ouadie, Amsil, Hamid, Benchrif, Abdelfettah, El Banni, Fadi
Published in International journal of energy research (01.12.2022)
Published in International journal of energy research (01.12.2022)
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Journal Article
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
Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid
Published in Annals of nuclear energy (01.06.2020)
Published in Annals of nuclear energy (01.06.2020)
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Journal Article