NIFS-081

FULL TEXT (PDF, 682 KB)


Author(s):

K. Takahata, N. Yanagi, T. Mito, J. Yamamoto, O.Motojima and LHDDesign Group, K. Nakamoto, S. Mizukami, K. Kitamura, Y. Wachi, H. Shinohara, K. Yamamoto, M. Shibui, T. Uchida and K. Nakayama

Title:

Design and Fabrication of Forced-Flow Coils as R&D Program for Large Helical Device

Date of publication:

Apr. 1991

Key words:

superconducting coil, helical coil, poloidal coil, forced-flow coil, cable-in-conduit conductor, Large Helical Device

Abstract:

As research and development of helical field coil and poloidal field coil for Large Helical Device (LHD), two forced-flow cooled NbTi superconducting coils (TOKI-TF, PF) have been designed and fabricated. The helical coil (TOKI-TF) is a 1/4 scale model of LHD. It has the major radius of 0.9 m, the minor radius of 0.25 m and pitch number of 4. Nominal current and maximum field were designed to be 8 kA and 2.8 T, respectively. Another coil (TOKI-PF) was fabricated for the demonstration of LHD poloidal field coils. It consists of two double-pancakes with the inner radius of 0.6 m and the outer radius of 0.82 m. Nominal current of 25 kA simulates that of LHD poloidal field coils. Cable-in-conduit type conductors were used for the both coils. The test facility was also constructed with a vacuum vessel, Iiquid nitrogen shield, 30 kA power leads, a heat exchanger, cryogenic supports and others. In this paper, design concepts and details will be presented.

List of NIFS Report (1991)Return toContents Page Return toNIFS Homepage
footer
 National Institute for Fusion Science
Copyright: 1995-2007 National Institute for Fusion Science (NIFS)
Address: 322-6,Oroshi-cho, Toki, GIFU, 509-5292, Japan
Telephone:+81-572-58-2222