Wendelstein 7-X

Physical and Technical Objectives



The Wendelstein 7-X stellarator, now being built at the Greifswald Branch Institute of IPP, is intended to demonstrate that fusion devices of the stellarator type are suitable for power plants:
  • Prove the success of the stellarator optimisation concept: Improved particle and energy confinement and stable plasma equilibrium under conditions like those in a power plant
  • Operation at maximum plasma pressure and beta values (plasma pressure relative to the counter pressure from the magnetic field)  of 4 to 5 percent, as required for a reactor
  • Application of effective non-ohmic heating methods to produce and heat the plasma under steady state conditions
  • Investigation of the impurity transport and development of methods of impurity control
  • Long-time and quasi-stationary operation for all device components
  • Control of plasma-wall interaction, particle recycling and refuelling under the conditions of continuous operation by means of a divertor at the plasma boundary

These objectives can be reached by an optimised magnetic field as realised in W7-X by a set of superconducting modular magnetic coils. The animation below illustrates the three-dimensionality and symmetry of the W7-X magnetic field coils and the stellarator plasma, for example the plasma cross section varying from bean to triangular shape.

Startbild W7-X Movie
Click to start animation (.mpg 150 MB)

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001: Coil shape is derived from plasma optimisation criteria

Coil shape is derived from plasma optimisation criteria



002: Magnet module of Wendelstein 7-X

Magnet module of Wendelstein 7-X



003: Divertor target (heat load 10 MW/m²)

Divertor target (heat load 10 MW/m²)