Published August 31, 1998 | Version v1
Journal article

On the role of dust in fusion devices

  • 1. A.M. Prokhorov General Physics Institute, Russian Academy of Sciences, Moscow (Russian Federation)
  • 2. Institut fuer Experimentalphysik II - Anwendungsorientierte Plasmaphysik, Ruhr-Universitat Bochum (Germany)

Description

The problem of dust in the vicinity of the walls of Controlled Thermonuclear Devices (CTD) is discussed. It is pointed out that the conditions in the scrape-off layer and divertor are similar to those in low-temperature plasma processing devices where dust is a common occurrence. In the absence of in situ dust diagnostic techniques for present day CTD plasmas, indirect indications of the possible role of dust are analyzed. The most recent data on after-discharge dust suggest that during a discharge dust is confined for a long time inside the edge plasma. It is emphasized that the CTD dust problem assumes more significance for future larger power loadings and longer operation times expected for new devices such as ITER. (physics of our days)

Availability note (English)

Available from http://dx.doi.org/10.1070/PU1998v041n08ABEH000431

Additional details

Publishing Information

Journal Title
Physics Uspekhi
Journal Volume
41
Journal Issue
8
Journal Page Range
p. 815-822
ISSN
1063-7869

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40071000
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DIAGNOSTIC TECHNIQUES; DIVERTORS; DUSTS; ITER TOKAMAK; OPERATION; PLASMA; PLASMA SCRAPE-OFF LAYER
Descriptors DEC
BOUNDARY LAYERS; CLOSED PLASMA DEVICES; LAYERS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS