Effects of divertor geometry on tokamak plasmas
Creators
- 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
- URL
- http://www.iop.org/;
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