Physics and engineering design for Wendelstein VII-X
At IPP Garching, the future experiment Wendelstein VII-X is being developed. A Helias configuration (Helical Advanced Stellarator) was chosen for its confinement and stability properties. The goals are to continue the development of the modular stellarator, to demonstrate the reactor capability of this stellarator line, and to achieve quasi-steady-state operation in a temperature regime above 5 KeV. This temperature regime can be reached in Wendelstein VII-X if neoclassical transport plus the anomalous transport found in Wendelstein VII-A prevails. A heating power of 20MW is applied to reach the reactor-relevant parameter regime. The magnetic field has 5 field periods; other basic data are : major radius R(0) = 6.5m, magnetic induction B(0) = 3T and stored magnetic energy W approximately 0.88 GJ. The average plasma radius is 0.65m. Superconducting coils are favoured because of their steady-state field, but pulsed water-cooled copper coils are also being investigated. Unlike planar circular magnetic field coils which experience only a radially directed force, twisted coil systems for Helias configurations have shown that the magnitudes of these radial and lateral force components are comparable. Based on a support model the mechanical stresses are calculated; all components of the stress tensor are of equal importance. Other studies are concerned with the many complex engineering aspects presented by the construction of non-planar superconducting coils.
Bibliographic Reference: Report: IPP 2/300 EN (1989) 38 pp.
Availability: Available from Max-Planck-Institut für Plasmaphysik, 8046 Garching-bei-München (DE)
Record Number: 199010333 / Last updated on: 1994-12-01
Original language: en
Available languages: en