Abstract
Normal conducting steady-state toroidal magnet systems are investigated, emphasis being placed on applications to large ignited next generation tokamaks. The study is based on water-cooled tape wound D coils. The data for the TF magnet systems are calculated in a consistent manner with a computer program including the plasma, shield, ohmic heating coil system, and geometric requirements for blanket modules, beam ducts, etc. An optimization procedure is used to find those TF coil systems which minimize cost-relevant quantities. The main results are that normal conducting TF coil systems of ignited next-generation tokamaks (following JET, TFTR, etc.) can be operated in a stationary mode and fed from the grid. Cost for electricity is a relatively small portion of the investment cost even in the case of long integral burn times (>107 s).
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
