IFMIF/EVEDA achievements overview

    Research outputpeer-review


    In a fusion reactor, the plasma based on a deuterium-tritium reaction generates high energy neutron flux interacting with the materials of the plasma facing components. In order to study the irradiated behavior of these materials, the International Fusion Materials Irradiation Facility (IFMIF) was conceived to generate these fusion relevant neutrons through D-Li stripping source. IFMIF is presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the Broader Approach agreement signed between EURATOM and Japanese Government in 2007. This agreement mandates the IFMIF/EVEDA project to validate the design of the different systems of IFMIF and to produce an integrated engineering design of IFMIF, together with the data necessary for future decisions on its construction and operation. While the Engineering Validation Activity (EVA) of the Lithium Target Facility and the Test Facility was completed by constructing prototypes, the EVA of the Accelerator Facility with the Linear IFMIF Prototype Accelerator (LIPAc) is still on-going at the Rokkasho Fusion Institute, Japan. This paper overviews the achievements in the previous phase ended on 31 March 2020 and the progress in the current phase to complete the commissioning of the LIPAc.

    Original languageEnglish
    Article number114258
    Number of pages5
    Journalfusion engineering and design
    StatePublished - Apr 2024


    This work was undertaken under the Broader Approach Agreement between the European Atomic Energy Community and the Government of Japan. The views and opinions expressed herein do not necessarily state or reflect those of the Parties to this Agreement. The authors thank all the members of the home institutions and research founders, especially those who have been involved in, or supported, the IFMIF/EVEDA project; the former IFMIF/EVEDA project leaders, P. Garin, H. Matsumoto, J. Knaster and P. Cara; the former project managers, K. Sakamoto, R. Heidinger, Y. Okumura, T. Nishitani, and S. O'hira.

    FundersFunder number
    IFMIF - International Fusion Materials Irradiation Facility
    EURATOM - European Atomic Energy Community

      ASJC Scopus subject areas

      • Civil and Structural Engineering
      • Nuclear Energy and Engineering
      • General Materials Science
      • Mechanical Engineering

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