Published 1981
| Version v1
Journal article
Ripple reduction poloidal field coils for tokamak fusion reactors
Description
Ripple Reduction Poloidal Field (RRPF) coils consist of dipole magnetic coils placed above and below the plane of a tokamak plasma in order to produce the vertical and shaping field needed for plasma equilibrium and at the same time to reduce the magnetic ripple from discrete toroidal field (TF) coils. A design is presented which reduces the ripple produced by 8 TF coils with INTOR dimensions from more than 2% to less than 0.1% throughout the plasma. With this design, it is found that the poloidal field from the coils can be adjusted independent of the ripple reduction. Coil currents are found for which there are computed free-boundary plasma equilibria with elongated cross section
Additional details
Publishing Information
- Journal Title
- Proc. Symp. Eng. Probl. Fusion Res.
- Journal Issue
- p. 87-90
- Series
- Proc. Symp. Eng. Probl. Fusion Res.
- ISSN
- 0145-5958
Conference
- Title
- 9. symposium on engineering problems of fusion research.
- Dates
- 26 - 29 Oct 1981.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14766123
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- INTOR TOKAMAK; MAGNET COILS; POLOIDAL FIELD DIVERTORS; SPECIFICATIONS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; DIVERTORS; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES
Optional Information
- Secondary number(s)
- CONF-811040--.