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Fusion Research Center
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A Tokamak Neutron Source for FFH Based on Iter Physics and Technology
Rotation velocities in the plasma edge driven viscously by scrape-off layer flows
A semi-automated procedure for creating geometry and background plasma input files for the GTNEUT 2d neutral particle transport code using the uedge plasma edge code
Comparison of theoretical and experimental heat diffusivities in the DIII-D edge plasma
Interpretation of particle pinches and diffusion coefficients in the edge pedestal of DIII-D H-mode plasmas
An investigation of some effects of drifts and magnetic field direction in the scrape-off layer and divertor of tokamak plasmas
2009 Annual Report
Representation of the plasma fluid equations in "Miller equilibrium" analytical flux surface geometry
Effect on the divertor and scrape-off layer plasma properties of the distribution of power and particle influxes from the core
Applications of the Miller equilibrium to extend tokamak computational models