ISSN:
1089-7623
Source:
AIP Digital Archive
Topics:
Physics
,
Electrical Engineering, Measurement and Control Technology
Notes:
In order to meet the objectives of safely operating, controlling, and optimizing a long-pulse ignited plasma in next-step devices (e.g., ITER), it will be necessary to measure accurately and reliably a wide range of plasma parameters. The choice of measurement techniques and design of the corresponding diagnostic systems will be strongly influenced by the specific measurement requirements and by the practical constraints arising from the harsh radiation environment, limited access, and the need for very high levels of reliability and availability. The experience gained on existing large tokamaks such as JET is a good starting point for the diagnostic design but the extrapolation to next step conditions is substantial and it is already obvious that it will not be possible to apply some of the established techniques. For some measurements new approaches are required and specific R&D is necessary. In this paper, the likely measurement requirements will be outlined and the practical constraints summarized. Potentially suitable measurement techniques will be identified and the problems of implementation briefly discussed. Attention will be concentrated on those areas where the most difficult problems are foreseen and where new approaches are required. © 1995 American Institute of Physics.
Type of Medium:
Electronic Resource
URL:
http://dx.doi.org/10.1063/1.1146389
