Target system of IFMIF/EVEDA in Japanese activities

M. Ida, S. Fukada, T. Furukawa, Y. Hirakawa, H. Horiike, T. Kanemura, H. Kondo, M. Miyashita, H. Nakamura, H. Sigiura, A. Suzuki, T. Terai, Y. Tsuji, H. Ushimaru, K. Watanabe, J. Yagi

Research output: Contribution to journalArticlepeer-review

4 Citations (Scopus)


The Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) have been started. As Japanese activities for the target system, the EVEDA Lithium (Li) Test Loop to simulate hydraulic and impurity conditions of the IFMIF Li loop is under design. The feasibility of the thermo-mechanical structure of the target assembly and the replaceable back-plate made of F82H and 316L stainless steel is a key research subject. Toward final validation at the EVEDA loop, diagnostics systems applicable to the high-speed free-surface Li flow and hot traps to control nitrogen and hydrogen in Li loop have been investigated. In the remote handling subject of target assemblies and the replaceable back-plates activated by irradiation up to 50 dpa/y, lip welds on 316L-316L by laser and dissimilar metal welds on F82H-316L are necessary. Water experiments and hydraulic/thermo-mechanical analyses of the back-plate are underway.

Original languageEnglish
Pages (from-to)1294-1298
Number of pages5
JournalJournal of Nuclear Materials
Issue number1-3
Publication statusPublished - Oct 1 2011

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering


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