Published 1981 | Version v1
Journal article

Ripple reduction poloidal field coils for tokamak fusion reactors

Creators

  • 1. Ga Inst of Technol, Atlanta, USA

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--.