Karakoç A. Molten Salt Tritium Breeding Materials in Fusion Reactors: A Neutronic Comparative Analysis for ITER. New Energy Exploit. Appl. [Internet]. 2025 Sep. 25 [cited 2025 Oct. 7];4(2):144-56. Available from: http://ojs.ukscip.com/index.php/neea/article/view/1413