Annual Report on Major Results and Progress of Fusion Research and Development Directorate of JAEA from April 1, 2006 to March 31, 2007

Fusion Research and Development Directorate

Japan Atomic Energy Agency
Naka-shi, Ibaraki-ken

(Received June 25, 2008)

  This annual report provides an overview of major results and progress on research and development (R&D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2006 to March 31, 2007, including those performed in collaboration with other research establishments of JAEA, research institutes, and universities.

  In JT-60, as a result of ferritic steel tiles (FSTs) installation to reduce the troidal field ripple and the application of the real time current profile control, high boot strap current fraction (~0.7) has successfully been sustained about 8 s. In addition, the conceptual design of JT-60SA, which was placed as a combined project of JA-EU Satellite Tokamak Programme under the Broader Approach Programme and JAEA's programme for national use, was progressed.

  In theoretical and analytical researches, studies on ITB events and their triggers, plasma shape effect on edge stability and driven magnetic island evolution in rotating plasmas were progressed. In the NEXT project, computer simulations of the plasma turbulence were progressed.

  In fusion reactor technologies, R&Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotoron up to 10min with 0.82MW was demonstrated. Also current density of the neutral beam injector has been extended to 146A/m² at 0.84MeV. In the ITER Test Blanket Module (TBM), designs and R&Ds of Water and Helium Cooled Solid Breeder TBMs including tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets and neutronics integral experiments with a blanket mockup were also progressed. For ITER and DEMO blankets, studies on neutron irradiation effects and ion irradiation effects on F82H steel characteristics were continued using HFIR, TIARA and so on. In the IFMIF program, transitional activities to EVEDA were continued.

  In the ITER Program, under the framework of the ITER Transitional Arrangements, the Design and R&D Tasks (ITA Tasks) have been carried out by the Participant Teams along the work plan. In FY 2006, JAEA has performed seventy-four ITA Tasks and has completed fifty-nine Tasks. In addition, the provisional activity for the establishment of Japan Domestic Agency has been performed. For "Broader Approach (BA)", the site of BA activity has been decided in Rokkasho (the ex-ITER candidate site).

  Finally, in fusion reactor design studies, a reactor concept of SlimCS was progressed from the view point of maintenance scheme.