Helically Symmetric Experiment

A stellarator is a magnetic confinement fusion device which generates all required magnetic fields to confine high temperature plasma by external magnetic coils. In contrast, in tokamaks and reversed field pinches, the magnetic field is created by the interaction of external magnets and an electrical current flowing through the plasma. The lack of this large externally driven plasma current makes stellarators suitable for steady-state fusion power plants.

However, due to non-axisymmetric nature of the fields, old stellarators have a combination of toroidal and helical modulation of the magnetic field lines, which leads to high transport of plasma out of the confinement volume at fusion-relevant conditions, solved in the Wendelstein 7-X which has a better particle confinement than the expected in ITER, and achieve plasma duration of 30 minutes. This large transport in old stellarators can limited their performance as fusion reactors.

This problem can be largely reduced by tailoring the magnetic field geometry. The dramatic improvements in computer modeling capability in the last two decades has helped to "optimize" the magnetic geometry to reduce this transport, resulting in a new class of stellarators called "quasi-symmetric stellarators". Computer-modeled odd-looking electromagnets will directly produce the needed magnetic field configuration. These devices combine the good confinement properties of tokamaks and the steady-state nature of conventional stellarators. The Helically Symmetric Experiment (HSX) at the University of Wisconsin-Madison is such a quasi-helically symmetric stellarator (helical axis of symmetry).

The magnetic field in HSX is generated by a set of 48 twisted coils arranged in four field periods. HSX typically operates at a magnetic field of 1 Tesla at the center of the plasma column. A set of auxiliary coils is used to deliberately break the symmetry to mimic conventional stellarator properties for comparison.

The HSX vacuum vessel is made of stainless steel, and is helically shaped to follow the magnetic geometry.

Plasma formation and heating is achieved using 28 GHz, 100 kW electron cyclotron resonance heating (ECRH). A second 100 kW gyrotron has recently been installed on HSX to perform heat pulse modulation studies.[2]

HSX has a large set of diagnostics to measure properties of plasma and magnetic fields. The following gives a list of major diagnostics and subsystems.

HSX has made and continues to make fundamental contributions to the physics of quasisymmetric stellarators that show significant improvement over the conventional stellarator concept. These include:

• Measuring large ion flows in the direction of quasisymmetry
• Reduced flow damping in the direction of quasisymmetry
• Reduced passing particle deviation from a flux surface
• Reduced direct loss orbits
• Reduced neoclassical transport
• Reduced equilibrium parallel currents because of the high effective transform

A large number of experimental and computational research works are being done in HSX by students, staff and faculties. Some of them are in collaboration with other universities and national laboratories, both in the USA and abroad. Major research projects at present are listed below:

• Effect of quasi-symmetry on plasma flows
• Impurity transport
• Radio frequency heating
• Supersonic plasma fueling and the neutral population
• Heat pulse propagation experiments to study thermal transport
• Interaction of turbulence and flows in HSX and the effects of quasi-symmetry on the determination of the radial electric field
• Equilibrium reconstruction of the plasma density, pressure and current profiles
• Effects of viscosity and symmetry on the determination of the flows and the radial electric field
• Divertor flows, particle edge fluxes
• Effect of radial electric field on the bootstrap current
• Effect of quasi-symmetry on fast ion confinement

• Official website
• Experimental Tests of Quasisymmetry in HSX. Talmadge Slide 4 compares with tokamak