Diagnostics Plan for the National Compact Stellarator Experiment
Authors: D. Johnson, T. Brown, H. Neilson, G. Schilling, H. Takahashi, M. Zarnstorff, M. Cole, E. Lazarus, and M. Fenstermacher
Date of PPPL Report: July 2002
Presented at: the Fourteenth Topical Conference on High Temperature Plasma Diagnostics, 8-11 July 2002, Madison, Wisconsin USA. Proceedings to be published by Review of Scientific Instruments.
The National Compact Stellarator Experiment (NCSX) is a stellarator-tokamak hybrid seeking to combine the good confinement, high beta and moderate aspect ratio of the tokamak with the quasi-steady-state operation and good stability properties of the stellarator. A preliminary list of measurement requirements, intended to satisfy the needs of the phased research plan, provides the basis for a full complement of plasma diagnostics. It is important to consider this full set, even at this early stage, to assess the adequacy of the stellarator design for diagnostic port access. The 3-D nature of the plasma is a measurement challenge, as is the necessity for high spatial resolution to assess the quality of magnetic surfaces. Other diagnostic requirements include the need for re-entrant views that penetrate the cryostat, for a convenient e-beam probe for field line mapping, and for a diagnostic neutral beam for active spectroscopy.