Published March 1991
| Version v1
Journal article
ITER: Design overview
Description
The ITER design, jointly conducted by Euratom, Japan, USSR and USA under the auspices of the IAEA, is progressing with an optimized tokamak machine, having a major radius of 6.0 m, magnetic field on axis of 4.85 T, and a nominal plasma current of 22 MA. This paper describes major parameters of the machine as well as the materials research and development. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 179-181
- Journal Issue
- pt.B
- Series
- J. Nucl. Mater.
- Journal Page Range
- 1173-1178
- ISSN
- 0022-3115
- CODEN
- JNUMA
Conference
- Title
- 4. international conference on fusion reactor materials (ICFRM-4).
- Dates
- 4-8 Dec 1989.
- Place
- Kyoto (Japan).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 22087014
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; DIVERTORS; FIRST WALL; ITER TOKAMAK; SHIELDS; SPECIFICATIONS; SUPERCONDUCTING COILS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES