article · Nuclear Technology

Development, Validation, and Comparison of an OpenMC-Based Transport-Depletion Model for the Moroccan TRIGA Mark II with MCNP6.2

2025Abdelmalek Essaâdi University

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Research topics

Nuclear reactor physics and engineering
Nuclear Materials and Properties
Nuclear Physics and Applications

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DOI: 10.1080/00295450.2025.2496058

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