Published July 1976
| Version v1
Report
The toroidal and poloidal magnetic field coils of the ASDEX Tokamak
Description
The design of the magnetic field coil system of the ASDEX tokamak is described. It consists of 16 toroidal field coils, producing a magnetic field of 3 T in the plasma center and of 54 poloidal field coils to induce the plasma current, to stabilize the plasma position and to produce an axisymmetric divertor field. (orig.)
Abstract (German)
In der vorliegenden Arbeit wird der Aufbau des Magnet-Systems des ASDEX Tokamak beschrieben. Es besteht aus 16 toroidalen Spulen, die ein Magnetfeld von 3 T im Zentrum des Plasmas erzeugen, und 54 poloidalen Spulen zur Induktion des Plasmastromes, zur Stabilisierung der Plasma-Lage und zur Erzeugung eines axial-symmetrischen Divertor-Feldes. (orig.)Additional details
Publishing Information
- Imprint Title
- Divertor Tokamak ASDEX
- Imprint Pagination
- p. 17-26.
- Report number
- IPP--III/27
Conference
- Title
- 6. symposium on engineering problems of fusion research.
- Dates
- 18 Nov 1975.
- Place
- San Diego, Calif. USA.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 8300297
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ASDEX TOKAMAK; AXIAL SYMMETRY; DIVERTORS; ELECTROMAGNETIC FIELDS; JOINTS; JOULE HEATING; MAGNET COILS; PLANNING; SPECIFICATIONS; TOKAMAK DEVICES; TOROIDAL CONFIGURATION; TRANSFORMERS
- Descriptors DEC
- ANNULAR SPACE; CLOSED PLASMA DEVICES; CONFIGURATION; ELECTRIC COILS; ELECTRICAL EQUIPMENT; HEATING; PLASMA HEATING; SYMMETRY; THERMONUCLEAR DEVICES
Optional Information
- Notes
- 5 figs.; 2 refs.