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Nuclear Applications

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Neutronic Analysis on Molten Salt Reactor (MSR) Using OpenMC Code With Variations of Geometry Core Fueled By LiF-BeF2-UF4
Authors: Ratna Dewi Syarifah , Briyanti Adelia Putri , Indarta Kuncoro Aji
Published: 2024 , El-Cezeri
DOI: 10.31202/ecjse.1364028
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