1. Divertor operation in stellarators: results from W7-AS and implications for future devices
- Author
-
M. Hirsch, R. Jaenicke, Suguru Masuzaki, A. Werner, D. Hildebrandt, P. Grigull, F. Sardei, Dirk Naujoks, U. Wenzel, H. Renner, F. Gadelmeier, Friedrich E. Wagner, Thomas Klinger, E. Pasch, W As Team, J. P. Knauer, R. Burhenn, H. Ehmler, J. Baldzuhn, N. Ramasubramanian, H. Niedermeyer, D. Hartmann, R. Brakel, J. Kisslinger, K. McCormick, Y. Feng, L. Giannone, R. König, and S. Bäumel
- Subjects
Physics ,Steady state ,Mechanical Engineering ,Nuclear engineering ,Divertor ,Plasma ,Radiation ,Fusion power ,law.invention ,Nuclear physics ,Large Helical Device ,Nuclear Energy and Engineering ,Extant taxon ,law ,General Materials Science ,Stellarator ,Civil and Structural Engineering - Abstract
The research on divertors for stellarators is at the beginning. Extensive studies are being prepared on large helical device (LHD) and W7-X. W7-AS is now being operated with an open island divertor (ID) which serves as a test bed for the W7-X diverter. The divertor enables access to a new NBI-heated, high-density operating regime with improved confinement properties. This regime-the high-density H-mode (HDH)-displays no evident mode activity, is extant above a threshold density and characterized by flat density profiles. high-energy- and low-impurity-confinement times and edge-localized radiation. Impurity accumulation, normally associated with ELM-free H-modes, is avoided. Quasi-steady-state discharges with n e up to 4 x 10 20 m -3 , edge radiation levels up to 90% and plasma partial detachment at the divertor targets can be simultaneously realized. The accessibility to other improved confinement modes in W7-AS (conventional H-mode anti OC-mode) is not restricted by the divertor. The results provide a promising basis for future experiments, in particular on W7-X, and recommend the ID as a serious candidate for solving the plasma exhaust problem in stellarators.
- Published
- 2003
- Full Text
- View/download PDF