Compact Ignition Tokamak (CIT) Central Solenoid Design and R&amp;D for a &ldquo;Bucked&rdquo; and for a &ldquo;Wedged&rdquo; Machine

R.J. Thome; B.A. Smith; R.D. Pillsbury, Jr.; M.M. Olmstead; J. Bates; R. Vieira &amp; J. Feng; P. Titus &amp; R.L. Myatt

doi:dx.doi.org/10.13182/FST91-A29483

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Home / Publications / Journals / Fusion Science and Technology / Volume 19 / Number 3P2A

Compact Ignition Tokamak (CIT) Central Solenoid Design and R&D for a “Bucked” and for a “Wedged” Machine

R.J. Thome, B.A. Smith, R.D. Pillsbury, Jr., M.M. Olmstead, J. Bates, R. Vieira & J. Feng, P. Titus & R.L. Myatt

Fusion Science and Technology / Volume 19 / Number 3P2A / May 1991 / Pages 1059-1064

Ignition Device / dx.doi.org/10.13182/FST91-A29483

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The CIT design has evolved recently from a system in which the central solenoid outer boundary interacts with the inner legs of the toroidal field coils for mutual radial support during operation, to a system in which the central solenoid is radially self-supporting. The machine has also undergone some dimensional changes with a resulting increase in the demand for the total flux swing by the poloidal field (PF) coil system from 61 to 75 volt-seconds. This paper summarizes features of the two central solenoid designs and selected requirements for fabrication and operation. It also presents an update on results from the R&D program for this 20+ tesla coil system, together with future plans.