Nuclear aspects of molten salt blankets

• Published in: Fusion engineering and design Vol. 69; no. 1; pp. 205 - 213
• Main Authors: Cheng, E.T, Merril, B.J, Sze, Dai-Kai
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.09.2003; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; Corrosion control; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Molten salt; Nuclear transmutation; Site dose; Tritium breeding; Corrosion control; Tritium breeding; Nuclear transmutation; Molten salt; Site dose; Tokamak; Coolant; Tritium; Fluorides; Neutron activation; Nuclear fusion reactor; Blanket; Depletion; Accident; Corrosion; Transmutation
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/S0920-3796(03)00339-9

Nuclear aspects of candidate molten salts, namely a mixture of LiF and BeF 2 (FLIBE) and a mixture of LiF, NaF, and BeF 2 (FLINABE), were investigated for application as blanket coolants in tokamak fusion power plants. Tritium breeding, blanket energy multiplication, and neutron transmutation of these salts were assessed. Neutron activation of FLIBE and FLINABE was evaluated and site-boundary dose due to a worst-case loss of vacuum accident was estimated. Formation of F 2, TF and T 2 during power plant operation was analyzed and issues relevant to corrosion of structural materials due to the fluorine and fluoride species was assessed. Mechanism to control the corrosion of structural materials due to TF has been identified. Depletion of LiF, BeF 2, and NaF in the salts was calculated and quantities of the make-up fluorides to be added into the salts were estimated.