Author/Authors :
Nakamura، نويسنده , , Hiroo and Agostini، نويسنده , , Pietro and Ara، نويسنده , , Kuniaki and Fukada، نويسنده , , Satoshi and Furuya، نويسنده , , Kazuyuki and Garin، نويسنده , , Pascal and Gessi، نويسنده , , Alessandro and Giusti، نويسنده , , David and Groeschel، نويسنده , , Friedrich and Horiike، نويسنده , , Hiroshi and Ida، نويسنده , , Mizuho and Kanenmura، نويسنده , , Takuji and Kondo، نويسنده , , Hiroo and Loginov، نويسنده , , Nikolai and Micciche، نويسنده , , Gioacchino and Miyashita، نويسنده , , Makoto and Nitti، نويسنده , , F.S. and Suzuki، نويسنده , , Akihiro and Terai، نويسنده , , Takayuki and Watanabe، نويسنده , , Kazuhiro and Yagi، نويسنده , , Juro and Yoshida، نويسنده , , Eiichi and Mikheyev، نويسنده , , A.، نويسنده ,
Abstract :
In International Fusion Materials Irradiation Facility (IFMIF), intense neutron flux (4.5 × 1017 n/m2 s) with a peak energy of 14 MeV are produced by means of two deuteron beams with a total current of 250 mA and maximum energy of 40 MeV that strike a liquid Li target circulating in a Li loop. Major design requirement is to provide a stable Li jet at a speed of 10–20 m/s with a surface wave amplitude on the Li flow less than 1 mm for handling of an averaged heat flux of 1 GW/m2 under a continuous 10 MW deuterium beam deposition. The target system consists of a target assembly, a replaceable back-plate, a Li main loop and a Li purification loop. In July 2007, Engineering Validation and Engineering Design Activities (EVEDA) started under Broader Approach. In this paper, status of the engineering design of the IFMIF Li target system performed in 2007/2008 is described. The future EVEDA tasks to develop the target system are also summarized.
Keywords :
EUROFER , remote handling , Radiation damage , DBTT , Design , IFMIF , Liquid lithium , neutron source , Target , F82H
