skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Design considerations for ITER magnet systems

Conference · · Fusion Technol.; (United States)
OSTI ID:6277655

The International Thermonuclear Experimental Reactor (ITER) is now completing a definition phase as a beginning of a three-year design effort. Preliminary parameters for the superconducting magnet system have been established to guide further and more detailed design work. Radiation tolerance of the superconductors and insulators has been of prime importance, since it sets requirements for the neutron-shield dimension and sensitively influences reactor size. The major levels of mechanical stress in the structure appear in the cases of the inboard legs of the toroidal-field (TF) coils. The cases of the poloidal-field (PF) coils must be made thin or segmented to minimize eddy current heating during inductive plasma operation. As a result, the winding packs of both the TF and PF coils includes significant fractions of steel. The authors present here preliminary ITER magnet systems design parameters taken from trade studies, design, and analyses performed by the Home Teams of the four ITER participants, by the ITER Magnet Design Unit in Garching, and by other participants at workshops organized by the Magnet Design Unit.

Research Organization:
Lawrence Livermore National Lab., Univ. of California, Livermore, CA (US)
OSTI ID:
6277655
Report Number(s):
CONF-881031-; TRN: 89-013954
Journal Information:
Fusion Technol.; (United States), Vol. 15:2; Conference: 8. topical meeting on technology of fusion energy, Salt Lake City, UT, USA, 9 Oct 1988
Country of Publication:
United States
Language:
English