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Jamal Al Zain

Observed names: Al Zain Jamal, J. Al-Zain, Jamal Al-Zain
ORCID: 0000-0003-2344-5021
Observed ORCID: 0000-0003-2344-5021
OpenAlex ID: A5073245167
Validation of BEAMnrc Monte Carlo model for a 12 MV photon beam
2017 · Maged Mohammed, T. El Bardouni, et al. · Journal of King Saud University - Science · 16
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
2021 · Jamal Al Zain, O. El Hajjaji, et al. · International Journal of Energy Research · 15
Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor
2019 · Jamal Al Zain, O. El Hajjaji, et al. · Nuclear Science and Engineering · 10
Validation of deterministic code DRAGON5 for the fuel depletion analysis of a PWR pin-cell benchmark
2021 · Jamal Al Zain, O. El Hajjaji, et al. · Radiation Physics and Chemistry · 9
Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactor
2023 · Mohamed Mira, O. El Hajjaji, et al. · Annals of Nuclear Energy · 8
OpenNTP: Implementation of the S N method in cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry
2020 · M. Lahdour, T. El Bardouni, et al. · Computer Physics Communications · 8
Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code
2018 · Jamal Al Zain, O. El Hajjaji, et al. · Journal of Radiation Research and Applied Sciences · 8
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Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux
2018 · Jamal Al Zain, O. El Hajjaji, et al. · Results in Physics · 8
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Analysis of Depletion and Inventory of the Fuel for the MNSR Research Reactor Using the Deterministic Code DRAGON5
2019 · Jamal Al Zain, O. El Hajjaji, et al. · Nuclear Technology · 5
Validation of GAMOS code based on Geant4 Monte Carlo for a 12 MV Saturne43 Linac
2018 · Jamal Al Zain, T. El Bardouni, et al. · Journal of King Saud University - Science · 5
Calculation of the activity inventory for the MNSR reactor using DRAGON4 code
2018 · Jamal Al Zain, O. El Hajjaji, et al. · Radiation Physics and Chemistry · 5
Feasibility of deterministic self-shielding models for Molten Salt Fast Reactor analysis using DRAGON5 code with ENDF/B-VIII.0 data library
2022 · Mohamed Mira, O. El Hajjaji, et al. · Progress in Nuclear Energy · 4
NTP-ERSN verification with C5G7 1D extension benchmark and GUI development
2020 · M. Lahdour, T. El Bardouni, et al. · Nuclear Engineering and Technology · 4
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Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assembly
2023 · Jamal Al-Zain, O. El Hajjaji, et al. · Nuclear Engineering and Design · 3
Benchmark Comparisons of OpenMC and DRAGON5 Codes for Calculating the Doppler Coefficient of Reactivity
2022 · Jamal Al-Zain, O. El Hajjaji, et al. · Moscow University Physics Bulletin · 3
Derivation of optimal process MOC parameters and analysis of the 2D C5G7 MOX benchmark using DRAGON5 code
2021 · Mohamed Mira, O. El Hajjaji, et al. · Nuclear Engineering and Design · 3
Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes
2019 · Jamal Al Zain, O. El Hajjaji, et al. · Radiation Physics and Chemistry · 3
Activity inventory of activated materials in distant components of the CENM TRIGA MARK II reactor for decommissioning planning
2024 · S. El Maliki El Hlaibi, T. El Bardouni, et al. · Progress in Nuclear Energy · 1
ERSN-OpenMC-Py: A python-based open-source software for OpenMC Monte Carlo code
2024 · M. Lahdour, T. El Bardouni, et al. · Computer Physics Communications · 1
Measurement of the Reactivity Coefficients and Neutron Flux of the SLOWPOKE-2 Reactor Using OpenMC
2023 · Afaf El Mtili, Otman El Hajjaji, et al. · International Journal on Engineering Applications (IREA) · 1
Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code
2019 · Jamal Al Zain, O. El Hajjaji, et al. · Moscow University Physics Bulletin · 1
Development, Validation, and Comparison of an OpenMC-Based Transport-Depletion Model for the Moroccan TRIGA Mark II with MCNP6.2
2025 · Mohamed Mira, O. El Hajjaji, et al. · Nuclear Technology
Validation of deterministic code OpenNTP for the analysis of the C5G7-1D benchmark with different configurations
2022 · M. Lahdour, T. El Bardouni, et al. · Applied Radiation and Isotopes
Calculation of the Reactivity Feedback Coefficients for the LEU Fuel of the MNSR Reactor Using DRAGON5/DONJON5 Codes
2021 · Jamal Al Zain, O. El Hajjaji, et al. · Physics of Particles and Nuclei Letters
Works count: 24
Citation count: 121
H-index: 8
I10-index: 3
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