Published November 2001 | Version v1
Journal article

Toroidal field coil and central solenoid modernization for Globus-M tokamak

Description

The Globus-M spherical tokamak placed in A.F. Ioffe Institute is in operation since March 1999. The Globus-M tokamak peculiarity is its small aspect ratio plasma properties (R/a=1.5). Major parameters of the Globus-M tokamak are: plasma major radius 0.36 m, plasma minor radius 0.24 m, toroidal magnetic field 0.5 T, plasma current 0.3 MA and pulse length 0.3 s. Manufacturing of toroidal field coils required high accuracy of processing and high quality of contact surfaces. Winding uniformity of the conductor, both between turns, and on layers in the radial direction was required for the central solenoid. The ability to change a toroidal field coil together with providing access to the vacuum vessel manholes without disassembly of the machine is discussed. Calculations indicating dependence of magnetic flux distribution from central solenoid winding quality are presented

Additional details

Identifiers

PII
S0920379601005014;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
58-59
Journal Issue
4
Journal Page Range
p. 901-905
ISSN
0920-3796
CODEN
FEDEEE

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
33044466
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
ASPECT RATIO; GLOBUS-M SPHEROMAK; MAGNET COILS; MAGNETIC FIELD CONFIGURATIONS; MAGNETIC FIELDS; MAGNETIC FLUX; SOLENOIDS
Descriptors DEC
CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Copyright
Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.