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17–22 Oct 2016
Kyoto International Conference Center
Japan timezone

Lithium and Tungsten Limiters for 3 MW of ECR Plasma Heating in Т-10 Tokamak. Design, first results

21 Oct 2016, 14:00
4h 45m
Kyoto International Conference Center

Kyoto International Conference Center

Takaragaike, Sakyo-ku, Kyoto 606-0001 Japan
Poster EXC - Magnetic Confinement Experiments: Confinement Poster 8

Speaker

Dr Igor Lyublinski (RfJSCRedStar)

Description

Application of powerful (up to 3 MW) ECR plasma heating in Т-10 tokamak with graphite limiters is pulled down with a problem of the plasma pollution at power input more than 2 MW. The use of carbon based limiters leads to formation of carbon films on a surface of a tokamak chamber wall essentially increasing of impurity flux and hydrogen recycling. For the solution of these problems the new tungsten and lithium limiters are developed. As it is supposed, application of tungsten as a plasma facing material will allow excluding carbon influx into vacuum chamber. An additional lithium limiter arranged in a shadow of tungsten one will be used as a lithium source for plasma periphery cooling due to a reradiation on lithium that will lead to decrease in power deposition on tungsten limiters. Parameters and design of limiters are presented. Lithium limiter can move with respect to last closed magnetic surface that allows regulating of incoming power flux and, as consequence, a lithium influx into plasma. Plasma facing surface of a limiter is made of capillary-porous system (CPS) with lithium. Porous matrix of CPS (W felt) provides stability of liquid lithium surface under MHD force effect and an opportunity of its constant renewal due to capillary forces. The necessary lithium flux from a lithium limiter surface is estimated for maintenance of normal operation mode of tungsten limiters at ECRH power of 3 MW during 400 ms. It is supposed, that Zeff of plasma would not exceed of 2 in this case and about 13 g of lithium deposit will be on the wall for the campaign of 1000 discharges. Thus, the upgrade of limiters in tokamak Т-10 will allow providing of ECR plasma heating with power up to 3 MW at reasonable lithium flux. Results of first experiments with complex of lithium and tungsten limiters on T-10 tokamak are presented.
Country or International Organization Russian Federation
Paper Number EX/P8-37

Primary author

Dr Igor Lyublinski (RfJSCRedStar)

Co-author

Dr Alexey Vertkov (JSC “Red Star”)

Presentation materials