Poloidal field coil and current distribution study for the Toroidal Fusion Core Experiment (TFCX). Draft [electronic resource].
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1983. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 7 : digital, PDF file
- Additional Creators:
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The Toroidal Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, current-driven, ''next step'' tokamak device. The poloidal field (PF) coil configuration has major impact on the size and cost of a tokamak machine. The purpose of this trade study was to determine the achievable values of plasma triangularity and elongation consistent with mechanical configuration and plasma performance requirements. The study was made with three sets of PF coil configurations: (1) PF coils external to the (TF) coil, (2) all PF coils inside the TF coil bore, and (3) a hybrid configuration with some coils inside and some outside of the TF coil bore. The impact of plasma shape, profile, and coil locations on the distance between the plasma boundary and separatrix are presented. It is concluded that the plasma scrape-off requirements for removing impurities with a single null limiter can only be satisfied if the triangularity is limited to approx. 0.30 for an elongation of 1.6.
- Published through SciTech Connect., 01/01/1983., "conf-831203-194", "DE85012345", 10. symposium on fusion engineering, Philadelphia, PA, USA, 5 Dec 1983., and Miller, J.; Strickler, D.J.; Srivastava, V.C.
- Funding Information:
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