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Internal resistive initiation coil electromagnetics in the FED/INTOR baseline design [electronic resource].

Published:
Los Alamos, N.M. : Los Alamos National Laboratory, 1981.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
Pages: 6 : digital, PDF file
Additional Creators:
Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
This study determined some of the electric requirements for radio-frequency nonassisted plasma initiation from normal conducting coils inside tokamak toroidal field coils in the presence of cryostats and other major structures. We also studied the effects of bellows or highly insulated sections. Depending on whether or not insulating sections are used, the field penetration time is 50 to 90 ms, the blip pulse length is 0.15 to 0.19 s, and the power supplied to the blip coils is 400 to 700 MW. Because of its plasma stabilizing effect, a highly conducting vacuum shell is recommended.
Report Numbers:
E 1.99:la-ur-81-2986
E 1.99: conf-811040-66
conf-811040-66
la-ur-81-2986
Subject(s):
Other Subject(s):
Note:
Published through SciTech Connect.
01/01/1981.
"la-ur-81-2986"
" conf-811040-66"
"DE82002363"
9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981.
Murray, J.G.; Vogel, H.F.; Bronner, G.
Funding Information:
W-7405-ENG-36
View MARC record | catkey: 14750411