Safety concept of the IFMIF/EVEDA lithium test loop

• Published in: Fusion engineering and design Vol. 86; no. 9; pp. 2433 - 2436
• Main Authors: Furukawa, Tomohiro, Kondo, Hiroo, Hirakawa, Yasushi, Kato, Shoichi, Matsushita, Izuru, Ida, Mizuho, Nakamura, Kazuyuki
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.10.2011; Elsevier
• Subjects: Abnormalities; Applied sciences; Controled nuclear fusion plants; Coolants; Dangerous; Design; Design engineering; Energy; Energy. Thermal use of fuels; EVEDA; Exact sciences and technology; Experimental methods and instrumentation for elementary-particle and nuclear physics; IFMIF; Installations for energy generation and conversion: thermal and electrical energy; Leak; Lithium; Neutron sources; Nuclear engineering; Nuclear physics; Nuclear safety; Particle sources and targets; Physics; Safety; Sodium; Design; IFMIF; Lithium; Safety; EVEDA; Leak; Neutron source; Nuclear fusion reactor; Safety measure; Coolant; Sodium; Fast reactor
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2010.12.037

In order to obtain engineering data on the lithium target system, which is the neutron source of the International Fusion Material Irradiation Facility (IFMIF), design and fabrication of the EVEDA Lithium Test Loop (ELTL) are being carried out under Engineering Validation and Engineering Design Activity (EVEDA). The ELTL holds 2500 kg of lithium. Since lithium is specified by Japanese law as a dangerous substance as in sodium, coolant for fast reactors, countermeasures which assume a lithium leak and other abnormalities are indispensable. This paper describes safety principles and measures decided under the detailed design process.