OVERVIEW OF W7-X DIAGNOSTICS

Citation
M. Kick et al., OVERVIEW OF W7-X DIAGNOSTICS, Fusion engineering and design, 34-5, 1997, pp. 817-821
Citations number
7
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
09203796
Volume
34-5
Year of publication
1997
Pages
817 - 821
Database
ISI
SICI code
0920-3796(1997)34-5:<817:OOWD>2.0.ZU;2-Z
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 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.