Validation of BEAMnrc Monte Carlo model for a 12 MV photon beam M Mohammed, T El Bardouni, E Chakir, M Saeed, L Mohamed Journal of King Saud University-Science 30 (4), 537-543, 2018 | 15 | 2018 |
Eigenvalue sensitivity and nuclear data uncertainty analysis for the Moroccan TRIGA Mark II research reactor using SCALE6. 2 and MCNP6. 2 H Ziani, T El Bardouni, M Lahdour, M El Barbari, H El Yaakoubi, ... Nuclear Engineering and Design 378, 111160, 2021 | 8 | 2021 |
Neutronic and burn‐up calculations of the (ThO2‐UO2) pin cell benchmark using DRAGON5 and MCNP6.2 codes with ENDF/B‐VIII.0 nuclear data library J Al Zain, O El Hajjaji, T El Bardouni, M Lahdour, T El Ghalbzouri International Journal of Energy Research 45 (8), 11538-11551, 2021 | 8 | 2021 |
Fuel reloads optimization for TRIGA research reactor using Genetic Algorithm coupled with neutronic and thermal-hydraulic codes E Chham, T El Bardouni, Y El Mghouchi, A Milena-Pérez, B El Bakkari, ... Progress in Nuclear Energy 133, 103637, 2021 | 7 | 2021 |
NTP-ERSN: a new package for solving the multigroup neutron transport equation in a slab geometry M Lahdour, T El Bardouni, E Chakir, K Benaalilou, M Mohammed, ... Applied Radiation and Isotopes 145, 73-84, 2019 | 7 | 2019 |
Sensitivity and uncertainty quantification of neutronic integral data in the TRIGA Mark II research reactor M Makhloul, H Boukhal, E Chakir, T El Bardouni, M Lahdour, M Kaddour, ... Nuclear Engineering and Technology 54 (2), 523-531, 2022 | 6 | 2022 |
Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors H El Yaakoubi, H Boukhal, T El Bardouni, L Erradi, E Chakir, K Benaalilou, ... Journal of King Saud University-Science 31 (4), 1271-1275, 2019 | 6 | 2019 |
Modeling and simulation of a TRIGA MARK-II research reactor using WIMSD-5B and CITATION codes K Benaalilou, T El Bardouni, Y Boulaich, H El Yaakoubi, E Chham, ... Applied Radiation and Isotopes 148, 64-75, 2019 | 6 | 2019 |
Validation of deterministic code DRAGON5 for the fuel depletion analysis of a PWR pin-cell benchmark J Al Zain, O El Hajjaji, T El Bardouni, M Lahdour Radiation Physics and Chemistry 186, 109545, 2021 | 5 | 2021 |
OpenNTP: Implementation of the SN method in cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry M Lahdour, T El Bardouni, O El Hajjaji, E Chakir, H Ziani, J Al Zain, ... Computer Physics Communications 261, 107812, 2021 | 4 | 2021 |
NTP-ERSN verification with C5G7 1D extension benchmark and GUI development M Lahdour, T El Bardouni, O El Hajjaji, E Chakir, M Mohammed, J Al Zain, ... Nuclear Engineering and Technology 53 (4), 1079-1087, 2021 | 3 | 2021 |
Analysis of depletion and inventory of the fuel for the MNSR research reactor using the deterministic code DRAGON5 J Al Zain, O El Hajjaji, T El Bardouni, M Lahdour Nuclear Technology 206 (4), 620-636, 2020 | 3 | 2020 |
The discrete ordinate method for angular flux calculations in slab geometry M Lahdour, T El Bardouni, M Mohammed, S El Ouahdani Heliyon 5 (8), 2019 | 3 | 2019 |
Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (TH) characteristics of the MNSR research reactor fuel assembly J Al-Zain, O El Hajjaji, T El Bardouni, AA Basfar, IA Alnaser, M Lahdour, ... Nuclear Engineering and Design 416, 112759, 2024 | 1 | 2024 |
Calculation of the activity inventory of the CENM TRIGA MARK II reactor for decommissioning planninig SEM El Hlaibi, T El Bardouni, Y Boulaich, E Chham, O El Hajjaji, A El Mtili, ... Radiation Physics and Chemistry 207, 110837, 2023 | 1 | 2023 |
Benchmark Comparisons of OpenMC and DRAGON5 Codes for Calculating the Doppler Coefficient of Reactivity J Al-Zain, O El Hajjaji, T El Bardouni, M Lahdour, M Mira, H Satti, ... Moscow University Physics Bulletin 77 (6), 922-929, 2022 | 1 | 2022 |
Neutronic modeling and calculation of the Nuclear Heating Reactor NHR-5 by the deterministic codes DRAGON5 & DONJON5 H El Yaakoubi, H Boukhal, L Erradi, E Chakir, T El Bardouni, M El Barbari, ... Progress in Nuclear Energy 142, 104000, 2021 | 1 | 2021 |
ERSN-OpenMC-Py: A python-based open-source software for OpenMC Monte Carlo code M Lahdour, T El Bardouni, O El Hajjaji, JEL Bakkali, J Al-Zain, ... Computer Physics Communications, 109121, 2024 | | 2024 |
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment H Ziani, T El Bardouni, C Elyounoussi, I Berriban, T El Ghalbzouri, ... Nuclear Technology 210 (1), 72-83, 2024 | | 2024 |
Validation of deterministic code OpenNTP for the analysis of the C5G7-1D benchmark with different configurations M Lahdour, T El Bardouni, O El Hajjaji, E Chakir, H Boukhal, J Al Zain, ... Applied Radiation and Isotopes 187, 110317, 2022 | | 2022 |