Fusion Engineering and Design 84 (2009) 252–258 Contents lists available at ScienceDirect Fusion Engineering and Design j o u r n a l h o m e p a g e : w w w . e l s e v i e r . c o m / l o c a t e / f u s e n g d e s Status of engineering design of liquid lithium target in IFMIF-EVEDA Hiroo Nakamura a,∗ , Pietro Agostini b , Kuniaki Ara a , Satoshi Fukada c , Kazuyuki Furuya d , Pascal Garin e , Alessandro Gessi b , David Giusti b , Friedrich Groeschel f , Hiroshi Horiike g , Mizuho Ida a , Takuji Kanenmura g , Hiroo Kondo a , Nikolai Loginov h , Gioacchino Micciche b , Makoto Miyashita a , F.S. Nitti b , Akihiro Suzuki i , Takayuki Terai i , Kazuhiro Watanabe a , Juro Yagi i , Eiichi Yoshida a , A. Mikheyev h a JAEA, Japan b ENEA, Italy c Kyusyu University, Japan d Hachinohe National College of Technology, Japan e IFMIF EVEDA Project team, Japan f FZK, Germany g Osaka University, Japan h IPPE-Obninsk, Russia i University of Tokyo, Japan a r t i c l e i n f o Article history: Available online 21 March 2009 Keywords: IFMIF Neutron source Liquid lithium Target F82H EUROFER Remote handling Radiation damage DBTT Design a b s t r a c t In International Fusion Materials Irradiation Facility (IFMIF), intense neutron flux (4.5 × 10 17 n/m 2 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/m 2 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. © 2009 Elsevier B.V. All rights reserved. 1. Introduction Development of materials for the fusion DEMO is one of key issues to realize fusion energy. For testing candidate materials to be used in the fusion DEMO reactor [1], the International Fusion Mate- rials Irradiation Facility (IFMIF) is under development. The IFMIF is an accelerator-based neutron source based on D-Li stripping reac- tion aimed at producing an intense neutron flux (4.5 × 10 17 n/m 2 s) with a peak energy of 14 MeV. To realize such a condition, two 40 MeV deuteron beams with a total current of 250 mA are injected into a liquid Li stream flowing with a speed of 20 m/s at maximum. In July 2007, Engineering Validation and Engineering Design Activ- ∗ Corresponding author at: IFMIF Development Group, Tokai Research and Devel- opment Center,Japan Atomic Energy Agency,2-4 Shirakata-Shirane,Tokai-mura, Ibaraki 319-1195, Japan. Tel.: +81 29 284 3791; fax: +81 29 282 5551. E-mail address: nakamura.hiroo@jaea.go.jp (H. Nakamura). ities (EVEDA) [2] started under Broader Approach [3] to establish final design for the IFMIF construction. The major requirements of the Li target system is to provide a stable Li jet under deuterium beam injection and intense neutrons emitted inside the Li flow- ing on a thin back-plate attached to the target assembly. Since the back-plate is operating under severe neutron irradiation condition (60 dpa/year), the back-plate is designed as a removable component to be replaced by a remote handling (RH) system. This paper describes status of engineering design of the IFMIF Li target including engineering validation. 2. Design requirements of IFMIF Li target The IFMIF Li target system shall be designed to have a capability of removal of 10 MW heat power produced by the deuterium beams, to produce a stable Li jet with a wave amplitude less than 1 mm at a speed of 10–20 m/s, to control level of the impurities (T, 7 Be, C, O, N) below permissible values, to have sufficient safety with respect 0920-3796/$ – see front matter © 2009 Elsevier B.V. All rights reserved. doi:10.1016/j.fusengdes.2009.02.019