Neutronic study of ThF4-UF4-LiF fuel mixture in the molten salt hybrid reactor for 233U denaturing

Progress in Nuclear Energy 2026

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Authors: Hacı Mehmet Şahin, Sümer Şahın, Güven Tunç, Hüseyin Şahiner
DOI: 10.1016/j.pnucene.2026.106237
Cited by: 0
References: 51

Fields of Study & Subjects

Nuclear reactor physics and engineering Nuclear Materials and Properties Fusion materials and technologies

Publication details

Journal / source
Progress in Nuclear Energy
Volume
193
Pages
106237–106237
Publication date
6 January 2026
Language
EN