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Impurity transport in Tokamak plasmas

, 2004
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A review on impurity transport in divertors

Journal of Nuclear Materials, 1997
Power exhaust is one of the most crucial requirements for future fusion reactors, like ITER. It is widely recognized that impurity injection is needed to significantly reduce the heat load to the divertor plates. By controlled injection of light impurities, the compatibility of high confinement core plasma with strong radiative divertor has been ...
A Sakasai
exaly   +3 more sources

Impurity production and transport at limiters

Journal of Nuclear Materials, 1989
Abstract This paper concentrates on the description and evaluation of experiments on the DITE tokamak. These are designed to characterise the processes involved in the production and transport of neutral and ionised impurities near carbon limiters. The need for good diagnostics in the scrape-off layer is highlighted.
G F Matthews
exaly   +2 more sources

Impurity transport and neoclassical predictions

Plasma Physics and Controlled Fusion, 1991
The authors present a brief review of collisional (classical and neoclassical) and anomalous transport. Particular emphasis is devoted to the question of charge independence of the anomalous transport coefficients and the combined action of anomalous and collisional transport.
Fussmann, G., Field, A., Kallenbach, A., Krieger, K., Steuer, K., ASDEX-Team   +5 more
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Turbulent Impurity Transport

AIP Conference Proceedings, 2008
Impurity transport is an important topic for ITER as impurity density in the core has to stay below a relative concentration of 5×10−5 [1] to reach ignition conditions. The reasons for that is mainly impurity radiation leading to cooling. In the edge region on the other hand site, higher impurity densities, going along with radiation energy losses are ...
Volker Naulin, Jens Juul Rasmussen, Clemente Angioni, Carine Giroud, Marco Valisa, Maria Ester Puiatti, L. Carraro, Sadruddin Benkadda   +7 more
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Impurity effects on drift wave stability and impurity transport

Nuclear Fusion, 1993
A numerical linear stability analysis of electrostatic ion temperature gradient (ITG) and dissipative trapped electron (DTE) modes in a three-component plasma (electrons, primary ions and impurity ions) is performed using a fully kinetic, sheared slab model. The quasi-linear particle and energy fluxes for each species are also computed.
R.R Dominguez, G.M Staebler
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Impurities and impurity transport in the spheromak SPHEX

Plasma Physics and Controlled Fusion, 1997
Absolute spectroscopic measurements are made of all significant ionization states of the dominant impurities in SPHEX during sustained operation, and these are compared with a diffusive transport model to derive average plasma parameters. Statistical tests are used to establish the reliability of these results.
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