Published 1979
| Version v1
Journal article
Toroidal field coil system for ''starfire'', a preliminary assessment
Description
An important element of the STARFIRE tokamak reactor is the 12-coil superconducting toroidal field coil system which is required to generate 5.6 tesla at the 7.0 m plasma axis, with a peak-to-peak field ripple of 1% (maximum). Internal spatial requirements dictate a clear bore about 15-1/2 m high * 10 m wide, resulting in a total stored energy of 67 GJ
Additional details
Publishing Information
- Journal Title
- Proc. Symp. Eng. Probl. Fusion Res.
- Journal Volume
- 3
- Journal Issue
- 79CH1441-5
- Series
- Proc. Symp. Eng. Probl. Fusion Res.
- Journal Page Range
- 1629-1633
Conference
- Title
- 8. symposium on engineering problems of fusion research.
- Dates
- 13 - 16 Nov 1979.
- Place
- San Francisco, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12626032
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTRICAL PROPERTIES; SPECIFICATIONS; STARFIRE TOKAMAK; SUPERCONDUCTING MAGNETS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR REACTORS
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; MAGNETS; PHYSICAL PROPERTIES; SUPERCONDUCTING DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Secondary number(s)
- CONF-791102--.