Abstract
The Wendelstein 7-X (W7-X) stellarator is the largest fusion experiment presently under construction. The main objective of W7-X is to prove the reactor relevance of a stellarator, based on the HELIAS principle, as an alternative to the tokamak. Details of the optimization criteria and the scientific and technical objectives can be found in several publications. At present, the construction of W7-X is close to the start of the assembly. The first superconducting nonplanar coil is undergoing acceptance testing, the first sector of the plasma vessel has been leak tested, the main parts for the outer vessel have been fabricated, the first ports are close to delivery, and many rigs for the assembly are already installed. The assembly started at the end of 2003 with the attachment of saddle coils for magnetic diagnostics on the plasma vessel and will last until 2009 when the torus will be closed. Start of plasma operation is scheduled for the middle of 2010.
Highlights
1 Introduction Wendelstein 7-X (W7-X) is a HELIAS-type stellarator which is optimized with regard to physics and engineering criteria [1]
4 Summary and outlook An overview is given on the current status of W7-X component construction and assembly
It can be stated that component final design and manufacture generally progresses well, and the situation concerning the coils and mechanical structure is under control
Summary
Wendelstein 7-X (W7-X) is a HELIAS-type stellarator which is optimized with regard to physics and engineering criteria [1]. The components inside the PV ("in-vessel components", IVC) comprise divertor target plates and baffles for energy and particle control, panels and heat shields for wall protection, control coils to modify the magnetic field, cryo-pumps, and the corresponding water, LN2 and supercritical He coolant supply lines Besides these aforementioned basic machine components a number of peripheral and auxiliary equipment is necessary for operation, like plasma heating systems (ECRH, ICRH and NBI), cooling water supply for the IVCs, the PV as well as port walls, the refrigeration system, the instrumentation, the gas and electricity supplies, etc. A series of quality problems, mainly in the termination areas, was discovered during the acceptance tests These were poor quality welds, leaks, and in particular imperfections of the electrical insulation within the terminations. Another four coils are waiting for the cryogenic tests in Saclay
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