Latest design of liquid lithium target in IFMIF

H. Nakamura, P. Agostini, K. Ara, S. Cevolani, T. Chida, M. Ciotti, S. Fukada, K. Furuya, P. Garin, A. Gessii, D. Guisti, V. Heinzel, H. Horiike, M. Ida, S. Jitsukawa, T. Kanemura, H. Kondo, Y. Kukita, R. Lösser, H. MatsuiG. Micciche, M. Miyashita, T. Muroga, B. Riccardi, S. Simakov, R. Stieglitz, M. Sugimoto, A. Suzuki, S. Tanaka, T. Terai, J. Yagi, E. Yoshida, E. Wakai

Research output: Contribution to journalArticlepeer-review

20 Citations (Scopus)


This paper describes the latest design of liquid lithium (Li) target system in International Fusion Materials Irradiation Facility (IFMIF). IFMIF is an accelerator-driven intense neutron source for fusion reactor materials testing. Two 40 MeV deuteron beams with a total current of 250 mA strikes a liquid Li target circulating in a Li loop. The Li target is to provide a stable Li jet at a speed of 10-20 m/s to handle an averaged heat flux of 1 GW/m2. A concaved Li flow is applied to avoid Li boiling. A cold trap and two kinds of hot trap are applied to control impurities (T, 7Be, C, O, N) below permissible levels. A back wall made of RAFM is located in the most severe region of neutron irradiation (50 dpa/year). System availability requires more than 95% during plant lifetime. EVEDA tasks including Li loop are now being performed under the Broader Approach.

Original languageEnglish
Pages (from-to)1007-1014
Number of pages8
JournalFusion Engineering and Design
Issue number7-9
Publication statusPublished - Dec 2008

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering


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