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 HEL
IAS (helical advanced stellarator) concept and its realization with su
perconducting coils. Special efforts have been made for diagnostics wh
ich are relevant for parameters related to the optimization of the con
figuration, e.g. very small Shafranov shift, reduced neoclassical tran
sport losses in LMFP and plateau, small bootstrap current and good con
finement of fast particles at high beta. The island divertor concept n
eeds exact local measurements in this region. Suitable diagnostics wil
l be installed. (C) 1997 Elsevier Science S.A.