An Impurity Control Test Facility (ICTF) for the Study of Fusion Reactor/Plasma Edge Materials
Fusion Science and Technology / Volume 8 / Number 1P2B / July 1985 / Pages 1766-1771
Plasma Heating, Impurity Control, and Fueling / Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) / dx.doi.org/10.13182/FST85-A40016
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A test facility has been designed for investigating many of the impurity control issues associated with fusion reactors. The facility is a steady-state, rf-stabilized mirror with high field and high pumping capability end cells. Analysis indicates that the ICTF should readily produce a plasma with typical parameters of Ne = 3 × 1018 m−3, Te = 50 eV, and Ti = 100 eV at each end cell. A heat load of ∼2 MW/m2 over areas of ∼1600 cm2 could be produced at each end with 800 kW of ICRH power. These conditions would provide a unique capability for examining issues such as erosion/redeposition behavior, properties of redeposited materials, high recycling regimes, plasma edge operating limits for high-Z materials, and particle pumping efficiencies for limiter and divertor designs.
