Open AccessImpurity Control Test Facility (ICTF) for the study of fusion reactor plasma/edge materials interactions
Author(s) -
J.N. Brooks,
R.F. Mattas,
D.A. Ehst,
C. D. Boley,
N. Hershkowitz
Publication year - 1984
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6791283
Subject(s) - divertor , limiter , plasma , impurity , fusion power , nuclear engineering , enhanced data rates for gsm evolution , atomic physics , materials science , steady state (chemistry) , analytical chemistry (journal) , physics , tokamak , electrical engineering , chemistry , nuclear physics , engineering , chromatography , telecommunications , quantum mechanics
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