Abstract
An overview of the W7-X concept, parameters and planned diagnostics is given. W7-X allows access for all fusion plasma relevant diagnostics, despite its complex three-dimensional geometry resulting from the HELIAS (helical advanced stellarator) concept and its realization with superconducting coils. Special efforts have been made for diagnostics which are relevant for parameters related to the optimization of the configuration, e.g. very small Shafranov shift, reduced neoclassical transport losses in LMFP and plateau, small bootstrap current and good confinement of fast particles at high β. The island divertor concept needs exact local measurements in this region. Suitable diagnostics will be installed.
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