TITLE

Plasma diagnostics for the CIT (invited)

AUTHOR(S)
Medley, S. S.; Young, K. M.; CIT Diagnostics Team
PUB. DATE
August 1988
SOURCE
Review of Scientific Instruments;Aug1988, Vol. 59 Issue 8, p1745
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
The primary mission of the Compact Ignition Tokamak (CIT) is to study the physics of alphaparticle heating in an ignited D-T plasma. A burn time of about 10τ[sub E] is projected in a divertor configuration with base-line machine design parameters of R = 2.10 m, a = 0.65 m, b = 1.30 m, I[sub P] = 11 MA, B[sub T] = 10 T, and 10-20 MW of auxiliary rf heating. Plasma temperatures and density are expected to reach T[sub e] (0) ∼ 20 keV, T[sub i] (0) ∼ 30 keV, and n[sub e] (0) ∼ 1 × 10[sup 21] m[sup -3]. The combined effects of restricted port access to the plasma, the presence of severe neutron and gamma radiation backgrounds, and the necessity for remote handling of in-cell components create challenging design problems for ail of the conventional diagnostics associated with tokamak operations. In addition, new techniques must be developed to diagnose the evolution in space, time, and energy of the confined alpha distribution as well as potential plasma instabilities driven by collective alpha-particle effects. The design effort for CIT diagnostics is presently in the conceptual phase, with activity being focused on the selection ora viable diagnostic set and the identification of essential research and development projects to support this process. A review of these design issues and other aspects impacting the selection of diagnostic techniques for the CIT experiment will be presented.
ACCESSION #
9781519

 

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