Physics and Engineering Design for Wendelstein VII-X
- 1 January 1990
- journal article
- research article
- Published by Taylor & Francis Ltd in Fusion Technology
- Vol. 17 (1), 148-168
- https://doi.org/10.13182/fst90-a29178
Abstract
The future experiment Wendelstein VII-X (W VII-X) is being developed at the Max-Planck-Institut für Plasmaphysik. A Helical Advanced Stellarator (Helias) configuration has been chosen because of its confinement and stability properties. The goals of W VII-X 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 >5 keV. This temperature regime can be reached in W VII-X if neoclassical transport plus the anomalous transport found in W VII-A prevail. A heating power of 20 MW will be applied to reach the reactor-relevant parameter regime. The magnetic field in W VII-X has five field periods. Other basic data are as follows: major radius R0 = 6.5 m, magnetic induction B0 = 3 T, stored magnetic energy W ≈ 0.88 GJ, and average plasma radius a = 0.65 m. Superconducting coils are favored 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 coils are subject to a lateral force component as well. Studies of various superconducting 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 being conducted are concerned with the many complex engineering aspects presented by the construction of nonplanar superconducting coils.Keywords
This publication has 10 references indexed in Scilit:
- Monte Carlo computations of neoclassical transportPhysics of Fluids, 1988
- Quasi-helically symmetric toroidal stellaratorsPhysics Letters A, 1988
- Neoclassical energy confinement in stellaratorsJournal of Computational Physics, 1987
- Solution of stellarator boundary value problems with external currentsNuclear Fusion, 1987
- Plasma transport coefficients for nonsymmetric toroidal confinement systemsPhysics of Fluids, 1986
- Representations for vacuum potentials in stellaratorsComputer Physics Communications, 1986
- Stable stellarators with medium β and aspect ratioPhysics Letters A, 1986
- Neoclassical flows and transport in nonaxisymmetric toroidal plasmasPhysics of Fluids, 1983
- A Monte-Carlo model of neutral-particle transport in diverted plasmasJournal of Computational Physics, 1982
- Some considerations on closed configurations of magnetohydrostatic equilibriumIl Nuovo Cimento B (1971-1996), 1968