Annual Report of Naka Fusion Research Establishment
From April 1, 2001 to March 31, 2002
Naka Fusion Research Establishment
Japan Atomic Energy Research Institute
Naka-machi, Naka-gun, Ibaraki-ken
(Received September 25, 2002)
This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, including those performed in collaboration with other research establishments of JAERI, during the period from April 1, 2001 to March 31, 2002. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, and completion of ITER Engineering Design Activities (EDA) in July 2001, including technology R&D.
Objectives of the JT-60 project are to contribute the physics R&D for ITER and to establish the physics basis for a steady state tokamak fusion reactor like SSTR. In this fiscal year, most of JT-60 experiments have been devoted to the improvement, sustainment and integration of the high plasma performance.
Highlights of JT-60 experiments are summarized as follows;
The highlights of technological progress in JT-60 are as follows;
Objectives of the JT-60SC program are to realize the high-beta steady-state operation of reactor-relevant plasmas and to demonstrate the compatibility of the reduced-activation ferritic steel with the plasma. Physics and engineering design of the JT-60SC made progress on the basis of the objectives.
On JFT-2M, advanced and basic research for the development of high performance tokamak plasma has been promoted, making use of the flexibility of a medium-sized device. In this fiscal year, inside wall of the vacuum vessel was fully covered with ferritic steel plates. A fine structure of the magnetic field inside the vacuum vessel was measured using a three-dimensional magnetic field measurement apparatus. In parallel with this program, advanced and basic study on H-mode plasmas and a compact toroid (CT) injection, etc. has been pursued on JFT-2M.
The principal objective of theoretical and analytical studies is to understand physics of tokamak plasmas. The dynamics of internal transport barrier formation and the relation between the core confinement and the L-mode base were investigated. Progress was also made on the study of MHD instabilities. Surveys on the universality of vertical displacement event (VDE), the effect of polarization current on neoclassical tearing mode (NTM), the feasibility of suppressing NTM by electron cyclotron current drive (ECCD) and divertor characteristics in JT-60SC were carried out. The NEXT (Numerical EXperiment of Tokamak) project has been progressed in order to research complex physical processes both in core and in divertor plasmas by using massively parallel computers. Substantial progresses were made in the studies of turbulence and MHD reconnection and codes were developed to analyze divertor transport in a realistic geometry.
Research and development of fusion reactor technologies have been carried out both to assure the technologies required for the construction of ITER and to accumulate technological data base to assure the design of DEMO, which include the development of the blanket for electric power generation and of reduced activation structural materials and their neutron irradiation facility. Major achievements in the area of fusion reactor technologies in this fiscal year are as follows;
In July 2001, nine-year ITER EDA was successfully completed. The first comprehensive design of a fusion experimental reactor based on well-established physics and technology was produced through the activities. The results of the design activities have been completely documented by the hierarchically organized ITER Final Design Report (FDR). The EDA R&D activities with extensive industrial involvement had demonstrated that the main ITER components can function properly.
Following the completion of the EDA, "Co-ordinated Technical Activities (CTA)" were started. CTA means technical activities which are deemed necessary to maintain the integrity of the international project, so as to prepare for ITER Joint Implementation. The central missions of CTA are design adaptation to the specific site(s) conditions, preparation of procurement documents, and assurance of the coherence of the ITER project including design control.
In fusion reactor design activities, a conceptual design of a power reactor with tight aspect ratio was newly proposed for cost reduction. Fuel supply by pellet injection and the erosion rate of the first wall by charge exchange neutrals and alpha particles were studied quantitatively in a fusion power reactor. High heat flux first walls, use of fusion power for fuel production and a reduction of radioactive wastes from the DEMO plant were mainly investigated from importance in socio-economic aspects.
|Editors||:||Ando, T., Matsumoto, H., Moriyama, S., Tanaka, F., Tuda, T., Tsuji, H.|
|Keywords||;||JAERI, Fusion Research, JT-60, JFT-2M, NEXT, Fusion Engineering, ITER, EDA, CTA, Fusion Reactor|