MABRURI, A. M.; SYARIFAH, R. D.; AJI, I. K.; HANIFAH, Z.; ARKUNDATO, A.; JATISUKAMTO, G. Neutronic analysis on molten salt reactor FUJI-12 using 235U as fissile material in LiF-BeF2-UF4 fuel . Eastern-European Journal of Enterprise Technologies, [S. l.], v. 5, n. 8(119), p. 6–12, 2022. DOI: 10.15587/1729-4061.2022.265798. Disponível em: https://journals.uran.ua/eejet/article/view/265798. Acesso em: 24 nov. 2024.