A 16-T Superconducting Toroidal Coil Development for a Tokamak Fusion Machine

Publisher Website
Google Scholar
Abstract
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.

This publication has 2 references indexed in Scilit: