The Alcator C-Mod diagnostic complement (invited) (abstract)
- MIT Plasma Fusion Center, Cambridge, Massachusetts 02139 (United States)
Alcator C-Mod is a high field, compact tokamak facility, which commenced operation in the fall of 1991. The device incorporates strong shaping and magnetic divertor capability, with high-power ICRF auxiliary heating and pellet fueling. Diagnosing the plasma properties of Alcator C-Mod poses numerous challenges. Detailed profile information will be required in order to understand the transport and confinement properties of the various regimes which will be explored. Diagnostic techniques which will be employed include laser scattering, interferometry, reflectometry, photon and particle spectroscopy, bolometry, and electric and magnetic probes. Parameters which will be measured include temperatures and densities (two-dimensional profiles in the confinement region), radiated power, {ital Z}{sub eff} , current density, fusion reactivity, MHD activity, and flux surface shape. Specific experiments to measure density and temperature fluctuations are also planned. Special emphasis has been placed on measurements of the properties of the edge plasma, with facilities to measure fueling and recycling fluxes, edge temperatures and densities (including neutrals), power flows, and impurity sources and transport in the limiter and divertor regions. This work is supported by U.S. Department of Energy Contract No. DE-AC02-78ET51013.
- DOE Contract Number:
- AC02-78ET51013
- OSTI ID:
- 7009325
- Journal Information:
- Review of Scientific Instruments; (United States), Vol. 63:10; ISSN 0034-6748
- Country of Publication:
- United States
- Language:
- English
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