KARAKOÇ, A. Molten Salt Tritium Breeding Materials in Fusion Reactors: A Neutronic Comparative Analysis for ITER. New Energy Exploitation and Application, [S. l.], v. 4, n. 2, p. 144–156, 2025. DOI: 10.54963/neea.v4i2.1413. Disponível em: http://ojs.ukscip.com/index.php/neea/article/view/1413. Acesso em: 7 oct. 2025.