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Author

Mohamed Mira

ORCID: 0000-0003-1576-3054
Observed ORCID: 0000-0003-1576-3054
OpenAlex ID: A5068363095
G4XRTube: A Geant4-based Monte Carlo application for X-ray tube simulation
2023 · Abdelghani Idrissi, Ibrahym Dourki, 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
Simulation of a NaI(Tl) Detector Model Using OpenMC Modified on Code Source and Validation Using Experimental and Simulated Results
2022 · Mohamed Drissi El-Bouzaidi, T. El Bardouni, et al. · Radiation Physics and Chemistry · 6
OpenMC-based high-fidelity model for the Moroccan TRIGA Mark II research reactor
2024 · Mohamed Mira, O. El Hajjaji, et al. · Progress in Nuclear Energy · 4
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
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
Development of a new steady-state thermal hydraulic and safety analysis code, OpenTHY, for a TRIGA MARK II research reactor
2025 · S. Oulad-Belayachi, Y. Boulaich, et al. · Applied Radiation and Isotopes · 2
Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation
2024 · Hicham Satti, Otman El Hajjaji, et al. · Nuclear Technology · 2
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
Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: Applying novel methodologies
2025 · Mohamed Mira, O. El Hajjaji, et al. · Annals of Nuclear Energy
Works count: 12
Citation count: 44
H-index: 4
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