13 Jun 2025
Development, Validation, and Comparison of an OpenMC-Based Transport-Depletion Model for the Moroccan TRIGA Mark II with MCNP6.2Publisher siteNuclear Technology, Nuclear reactor physics and engineering
Active, last published 2026
In nuclear reactor physics and engineering
Mohamed
Mira
Scholar“Research focused on Nuclear reactor physics and engineering and adjacent fields.”
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01 · About the work
What I study
ohamed Mira is a researcher working on Nuclear reactor physics and engineering. A fuller summary will appear once they update their profile.
02 · Reach
Publication output and reach
Mohamed's work has been cited 41 times across 4 active years. Bars show publications per year; the line shows cumulative citation totals across publications first appearing in each year.
03 · Research focus
Topics
Nuclear reactor physics and engineering×10Nuclear Materials and Properties×6Nuclear Physics and Applications×6Graphite, nuclear technology, radiation studies×5Nuclear Engineering Thermal-Hydraulics×2
04 · Where I am
Affiliations
Affiliation on published researchAbdelmalek Essaâdi University, MoroccoDrawn from the institution listed on this researcher’s published work.
Research themes (UN SDGs)
05 · Selected work
Recent publications
10 works13 May 2025
Development of a new steady-state thermal hydraulic and safety analysis code, OpenTHY, for a TRIGA MARK II research reactorPublisher siteApplied Radiation and Isotopes, Nuclear reactor physics and engineering
18 Mar 2025
Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: Applying novel methodologiesPublisher siteAnnals of Nuclear Energy, Nuclear reactor physics and engineering
29 Aug 20242cites
Advancing Fixed-Source Reactor Analysis Through OpenNode ImplementationPublisher siteNuclear Technology, Nuclear reactor physics and engineering
16 Jan 20243cites
OpenMC-based high-fidelity model for the Moroccan TRIGA Mark II research reactorPublisher siteProgress in Nuclear Energy, Nuclear reactor physics and engineering
15 Nov 20233cites
Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assemblyPublisher siteNuclear Engineering and Design, Nuclear reactor physics and engineering
7 Jul 20237cites
Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactorPublisher siteAnnals of Nuclear Energy, Nuclear reactor physics and engineering
24 Feb 2023Open access9cites
G4XRTube: A Geant4-based Monte Carlo application for X-ray tube simulationPublisher siteRadiation Physics and Chemistry, Radiation Therapy and Dosimetry
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