NSTX Report on FES Joint Facilities Research Milestone 2010
Authors: R. Maingi, J-W. Ahn, T.K. Gray, A.G. McLean, V.A. Soukhanovskii
Abstract:
Annual Target: Conduct experiments on major fusion facilities to improve
understanding of the heat transport in the tokamak scrape-off layer (SOL) plasma,
strengthening the basis for projecting divertor conditions in ITER. The divertor heat flux
profiles and plasma characteristics in the tokamak scrape-off layer will be measured in
multiple devices to investigate the underlying thermal transport processes. The unique
characteristics of C-Mod, DIII-D, and NSTX will enable collection of data over a broad
range of SOL and divertor parameters (e.g., collisionality ν*, beta β, parallel heat flux q||,
and divertor geometry). Coordinated experiments using common analysis methods will
generate a data set that will be compared with theory and simulation.
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Submitted to: PPPL Reports
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Download PPPL-4610 (pdf KB pp)
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