Review of JAEA activities on the IFMIF liquid lithium target in FY2005
Ida, Mizuho; Nakamura, Hiroo; Chida, Teruo; Sugimoto, Masayoshi
The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based Deuterium-Lithium (D-Li) neutron source to produce intense high energy neutrons (2 MW/m) up to 200 dpa and a sufficient irradiation volume (500 cm) for testing candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid Li flow with a speed of 20 m/s. In target system, radioactive species such as Be, tritium and activated corrosion products are generated. In addition, back wall operates under severe conditions of neutron irradiation damage (about 50 dpa/y). In this paper, the thermal structural analysis and the accessibility evaluation of the IFMIF Li loop are summarized as JAEA activities on the IFMIF target system performed in FY2005.