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Edge Minority Heating Experiment in Alcator C-Mod
Author(s) -
S.J. Zweben,
J. Terry,
P. Bonoli,
R. Budny,
C.S. Chang,
C. Fiore,
G. Schilling,
S.J. Wukitch,
J. Hughes,
Y. Lin,
R. B. Perkins,
M. Porkolab,
the Alcator C-Mod Team
Publication year - 2005
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/838133
Subject(s) - alcator c mod , tokamak , plasma , enhanced data rates for gsm evolution , ion , cyclotron , atomic physics , physics , power (physics) , computational physics , nuclear physics , engineering , telecommunications , quantum mechanics
An attempt was made to control global plasma confinement in the Alcator C-Mod tokamak by applying ion cyclotron resonance heating (ICRH) power to the plasma edge in order to deliberately create a minority ion tail loss. In theory, an edge fast ion loss could modify the edge electric field and so stabilize the edge turbulence, which might then reduce the H-mode power threshold or improve the H-mode barrier. However, the experimental result was that edge minority heating resulted in no improvement in the edge plasma parameters or global stored energy, at least at power levels of radio-frequency power is less than or equal to 5.5 MW. A preliminary analysis of these results is presented and some ideas for improvement are discussed

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