| A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor O Kabach, A Chetaine, A Benchrif, H Amsil, F El Banni International Journal of Energy Research, 2021 | 16 | 2021 |
| Processing of JEFF-3.3 and ENDF/B-VIII. 0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX O Kabach, A Chetaine, A Benchrif Applied Radiation and Isotopes 150, 146-156, 2019 | 16 | 2019 |
| 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 O Kabach, A Chetaine, A Benchrif, H Amsil Nuclear Engineering and Design 384, 111476, 2021 | 14 | 2021 |
| Neutronic and burnup characteristics of potential dual‐cooled annular (Th‐233U‐235U)O2 fuel for the advanced pressurized water reactors: An assembly‐level … Z Benrhnia, A Chetaine, O Kabach, H Amsil, A Benchrif, F El Banni International Journal of Energy Research 46 (15), 23501-23516, 2022 | 9 | 2022 |
| 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 … K Ouadie, C Abdelouahed, J Abdelhamid, D Abdelaziz, S Abdelmajid Nuclear Engineering and Technology 49 (8), 1610-1616, 2017 | 9 | 2017 |
| Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis O El Kheiri, O Kabach, A Chetaine Progress in Nuclear Energy 160, 104680, 2023 | 8 | 2023 |
| Analysis of reactivity control coefficients and the stability of an AP1000 reactor assembly fueled with (Th-233U) O2 using DRAGON code Z BENRHNIA, O KABACH, A CHETAINE, A SAIDI, H AMSIL, A BENCHRIF, ... Annals of the University of Craiova, Physics, 2023 | 8 | 2023 |
| 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 O Kabach, A Chetaine, A Benchrif, H Amsil Annals of Nuclear Energy 140, 107075, 2020 | 8 | 2020 |
| 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 O Kabach, A Chetaine, A Benchrif, H Amsil Nuclear Engineering and Technology 53 (8), 2445-2453, 2021 | 7 | 2021 |
| 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 F El Banni, O Kabach, A Boko, BLH Gogon, AA Koua, GA Monnehan, ... Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 44 …, 2022 | 5 | 2022 |
| Neutron beam characterization for the Moroccan TRIGA Mark II reactor H Amsil, A Jalil, O Kabach, H Chahidi, H Bounouira, C Elyounoussi, ... Journal of Radioanalytical and Nuclear Chemistry 327, 1063-1072, 2021 | 5 | 2021 |
| Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly T Bouassa, O Kabach, A Chetaine, Z Benrhnia, F El Banni, A Saidi Nuclear Engineering and Design 414, 112533, 2023 | 4 | 2023 |
| Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study M Lkouz, O Kabach, A Chetaine, A Saidi, T Bouassa Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 45 …, 2023 | 4 | 2023 |
| Neutronic feasibility study of (Th-233U)-ZrH1. 65 fuel in a modelled TRIGA research reactor F El Banni, O Kabach, AA Koua, BLH Gogon, GA Monnehan, A Benchrif, ... Journal of King Saud University-Science 34 (2), 101769, 2022 | 4 | 2022 |
| Neutronic Analysis of Moroccan TRIGA MARK-II Research Reactor using the DRAGON. v5 and TRIVAC. v5 codes A DARIF, A CHETAINE, O KABACH, M MGHAR, A SAIDI Annals of the University of Craiova, Physics 27 (41-49), 2017 | 4 | 2017 |
| Physical protection system, corrective actions, and weaknesses identification based on nuclear security series: The hypothetical atomic research institute (HARI) case O Kabach International Journal of Nuclear Security 6 (1), 4, 2020 | 3 | 2020 |
| 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 A Darif, A Chetaine, M Mghar, O Kabach Turkish Journal of Physics 42 (1), 41-46, 2018 | 3 | 2018 |
| 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 … O KABACH, A CHETAINE, A DARIF, A JALIL, A SAIDI, A BENCHRIF, ... Annals of the University of Craiova, Physics 28 (78-98), 2019 | 2 | 2019 |
| OpenMC Monte Carlo modelling of TRIGA research reactor A Jalil, A Chetaine, O Kabach, H Amsil, K Embarch, K Laraki, H Marah The Fourth International Conference on Physics and Technology of Reactors …, 2018 | 2 | 2018 |
| Generation of thermal scattering cross sections for Sapphire (Al2O3) and Bi Crystal filters used in nuclear facilities J ABDELHAMID, A HAMID, C ABDELOUAHED, K OUADIE, ... Physics AUC 29, 45, 2019 | 1 | 2019 |
Abdelfettah BENCHRIFScientist Researcher- CNESTEN在 cnesten.org.ma 的电子邮件经过验证
