Published November 1986 | Version v1
Journal article

A 16-T superconducting toroidal coil development for a tokamak fusion machine

  • 1. Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki-ken, 311-02

Description

In order to enable a compact design of the next generation tokamak, 16 T is desired as the maximum magnetic field of its toroidal coil. In Japan Atomic Energy Research Institute (JAERI), for the development of the 16-T toroidal coil, the one-meter-size 16-T demonstration coil program is now being discussed for the next project. As the research and development work for the high field toroidal coil, the segment test program, the FC program and the PHOENIX program are in progress. These programs have showed excellent results and is now going toward the 16-T demonstration coil as the target

Additional details

Publishing Information

Journal Title
Fusion Technol.
Journal Volume
10
Journal Issue
3
Series
Fusion Technol.
Journal Page Range
1513-1517
ISSN
0748-1896
CODEN
FUSTE

Conference

Title
7. topical meeting on the technology of fusion energy.
Dates
15-19 Jun 1986.
Place
Reno, NV (USA).

Optional Information

Secondary number(s)
CONF-860652--.