Annual Report of Fusion Research and Development Directorate of JAEA
from April 1, 2007 to March 31, 2008

Fusion Research and Development Directorate

Japan Atomic Energy Agency
Naka-shi, Ibaraki-ken

(Received October 20, 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, 2007 to March 31, 2008, including those performed in collaboration with other directorates of JAEA, research institutes, and universities.

  The JT-60U operation regime was extended toward the long sustainment of high normalized beta (βN) with good confinement (βN = 2.6 × 28 s). Effectiveness of real-time control of current profile was demonstrated in high β plasmas. Toroidal momentum diffusivity and the convection velocity were systematically clarified for the first time, and intrinsic rotation due to pressure gradient was discovered. Effects of toroidal rotation and magnetic field ripple on type I ELM size and pedestal performance were clarified, and type I ELM control was demonstrated by toroidal rotation control. Variety of inter-machine experiments, such as JT-60U & JET, and domestic collaborations were performed.

  In theoretical and analytical researches, for the NEXT (Numerical Experiment of Tokamak) project, numerical simulations of a tokamak plasma turbulence progressed and a zonal field generation was investigated. Also, nonlinear MHD simulations found the Alfven resonance effects on the evolution of magnetic islands driven by externally applied perturbations. Integrations of several kinds of element codes progressed in the integrated transport/MHD model, the integrated edge/pedestal model and the integrated SOL/divertor model.

  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 gyrotron up to 800 s with 1 MW was demonstrated. Also extracted beam current of the neutral beam injector has been extended to 320 mA at 796 keV. In the ITER Test Blanket Module (TBM), designs and R&Ds on Water and Helium Cooled Solid Breeder TBMs were progressed. For the ITER TBM fabrication technology, a full-scale TBM first wall was fabricated with reduced-activation-ferritic-martensitic steel (F82H) by a hot isostatic press method. 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.

  ITER Agreements entered into force on 24th October 2007. On the same day ITER Organization (IO) was established and JAEA was designated as the Japanese Domestic Agency (JADA) by Japanese Government. The Procurement Arrangement for the Toroidal Field (TF) Conductors was concluded between the IO and JADA in Nov. 2007, and then the contract with Japanese companies to fabricate TF conductors was launched in March 2008. The Quality Assurance Program of JADA inevitable to implement the procurement was approved by the IO. The Project Management (e.g. Schedule Management, Procurement Management, and QA) of JADA was executed. The preparation of the procurement was continued for the TF coil, Blanket First Wall, Divertor, Remote maintenance System of Blanket, EC and NB Heating System, and Diagnostics.

  The Agreement for the Broader Approach (BA) Activities entered into force and JAEA was assigned as the Implementing Agency for the BA Activities, on 1st June 2007. Contracts for the constructions of the buildings for the IFERC Project and the IFMIF/EVEDA Project as well as the preparation for the Rokkasho site were made in March 2008. For the IFERC Project, information exchange to obtain common view of DEMO design was carried out. Procurement Arrangement for the urgent tasks to be implemented for DEMO R&D was concluded. Preparation toward selection of a super computer for the Computational Simulation Centre started. For the IFMIF/EVEDA Project, detailed planning for the initial engineering research of the accelerator components, the lithium target and the test cell were implemented. On JT-60SA project, Executive Summary of the Conceptual Design Report including the baseline project schedule was approved at the 1st BA Steering Committee Meeting. The Integrated Project Team, consisting of the Project Team, JAEA Home Team and EU Home Team, was organized and developed the Integrated Design. The Procurement Arrangements were launched between the Implementing Agencies, JAEA and F4E, for the supply of PF magnet conductor and winding building, vacuum vessel and materials of in-vessel components.

  Finally, as to fusion reactor design study, physics design on current drive and beta limit analysis and neutronics design on the blanket for SlimCS progressed.

Editors : Kubo, H., Hoshino, K., Isei, N., Nakamura, H., Sato, S., Shimada, K., Sugie, T.
Keywords ; Fusion Plasma, Fusion Technology, JT-60, JT-60SA, ITER, Broader Approach, IFMIF/EVEDA, International Fusion Energy Research Center, DEMO Reactor