Published June 2001 | Version v1
Journal article

Effects of divertor geometry on tokamak plasmas

  • 1. European Fusion Development Agreement-Close Support Unit Garching, Max-Planck-Institut fuer Plasmaphysik, Garching (Germany)

Description

The design, construction and operation of advanced divertors have been the main topics of tokamak research during the last decade. The design of these divertors (carried out with two-dimensional plasma modelling codes) has been optimized to provide: a large operating density range for partially detached plasmas with large radiative losses; satisfactory particle control by efficient deuterium pumping; and He exhaust capability sufficient to remove fusion ashes when extrapolated to next step devices. This article explains the criteria that have guided this optimization process and then critically reviews the experimental evidence that confirms or refutes the physics-based design criteria on which the various existing advanced divertors have been based. (author)

Availability note (English)

Available online at the Web site for the journal Plasma Physics and Controlled Fusion (ISSN 1361-6587) http://www.iop.org/

Additional details

Identifiers

Publishing Information

Journal Title
Plasma Physics and Controlled Fusion
Journal Volume
43
Journal Issue
6
Journal Page Range
p. R183-R224
ISSN
0741-3335

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
32024731
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
DESIGN; DIVERTORS; ENERGY LOSSES; FABRICATION; HELIUM ASH; MATHEMATICAL MODELS; PUMPING; TOKAMAK DEVICES
Descriptors DEC
CHARGED PARTICLES; CLOSED PLASMA DEVICES; HELIUM IONS; IONS; LOSSES; THERMONUCLEAR DEVICES