Abstract
A concept of demountable toroidal field magnets for a compact fusion reactor is discussed. The magnets generate a magnetic field of 9.2 T on axis, in a 3.3 m major radius tokamak. Subcooled YBCO conductors have a critical current density adequate to provide this large magnetic field, while operating at 20 K reduces thermodynamic cooling cost of the resistive electrical joints. Demountable magnets allow for vertical replacement and maintenance of internal components, potentially reducing cost and time of maintenance when compared to traditional sector maintenance. Preliminary measurements of contact resistance of a demountable YBCO electrical joint between are presented.
Highlights
The recent development of YBCO superconducting tapes and cabling methods could be a revolutionary development for magnetic fusion
We developed a concept of demountable toroidal field coils for a fusion reactor, with preliminary stress and heating simulations
Demountable toroidal field magnets can have a large impact in reducing fusion reactors design limitations
Summary
- Performance correlation between YBa2Cu3O7 coils and short samples for coil technology development X Wang et al. - Advances on the Design of Demountable Toroidal Field Coils With REBCO Superconductors for an ARIES-I Class Fusion Reactor Franco J. - Effect of the axial stress and the magnetic field on the critical current and the electric resistance of the joints between HTS coated conductors K Konstantopoulou et al. Journal of Physics: Conference Series 507 (2014) 032030 doi:10.1088/1742-6596/507/3/032030. Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139, USA
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