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Status of engineering design of liquid lithium target in IFMIF-EVEDA

IFMIF-EVEDAの液体リチウムターゲットの工学設計の現状

中村 博雄; Agostini, P.*; 荒 邦章; 深田 智*; 古谷 一幸*; Garin, P.*; Gessii, A.*; Giusti, D.*; Groeschel, F.*; 堀池 寛*; 井田 瑞穂; 金村 卓治; 近藤 浩夫; Loginov, N.*; Micciche, G.*; 宮下 誠; Nitti, F. S.*; 鈴木 晶大*; 寺井 隆幸*; 渡辺 一慶; 八木 重郎*; 吉田 英一; Mikheyev, A.*

Nakamura, Hiroo; Agostini, P.*; Ara, Kuniaki; Fukada, Satoshi*; Furuya, Kazuyuki*; Garin, P.*; Gessii, A.*; Giusti, D.*; Groeschel, F.*; Horiike, Hiroshi*; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Loginov, N.*; Micciche, G.*; Miyashita, Makoto; Nitti, F. S.*; Suzuki, Akihiro*; Terai, Takayuki*; Watanabe, Kazuyoshi; Yagi, Juro*; Yoshida, Eiichi; Mikheyev, A.*

In IFMIF, target system consists of a target assembly, a Li main loop and a Li purification loop. In this paper, status of the engineering design of the IFMIF Li target system performed in 2007/2008 will be described. Major design requirement is to provide a stable Li at a speed of 10 m/s to 20 m/s. To realize stable Li flow, modification of the backplate with nearly constant radius curvature is applied. 3D thermal-hydraulic analysis of the Li target flow is in progress. By a hot trap, nitrogen concentration shall be controlled below 10 wppm. Tritium concentration shall be controlled by an yttrium hot trap below 1 wppm. The back-plate made of RAFM steel shall be used under intense neutron irradiation (50 dpa/y). To mitigate irradiation damage of the backplate, in-situ annealing up to 600$$^{circ}$$C is considered. To replace the backplate, two design options of the remote handling systems are under investigation.

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パーセンタイル:12.45

分野:Nuclear Science & Technology

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