TJ-II:Limiter

TJ-II has two mobile limiters, located in sectors A3 and C3 (115.5º and 295.5º), with a toroidal separation of 180º. ^[1] The limiters are fitted with Langmuir probes and gas injection ports. ^[2] ^[3] ^[4] A biasing voltage can be applied. ^[5]

TJ-II Limiter and plasma

TJ-II Limiter: photograph taken from port B8TANG (the location of the fast camera)

Liquid Lithium limiters

Liquid Lithium Limiter with Capillary Porous System

Currently (2010) a limiter upgrade is being prepared, consisting of liquid lithium limiters. ^[6] ^[7]

References

[1] E. de la Cal et al, The diagnosed mobile limiters of the TJ-II stellarator for plasma boundary studies, J. Nucl. Mat. 266-269 (1999) 485

[2] E. de la Cal, B. Brañas, F.L. Tabarés, D. Tafalla, A.L. Fraguas, M.A. Pedrosa, V. Tribaldos, E. Ascasibar, J. Herranz, I. Pastor and TJ-II Team, Plasma boundary and SOL studies of ECH-plasmas in TJ-II stellarator with diagnosed mobile poloidal limiters, Journal of Nuclear Materials, 290-293 (2001) 579-583

[3] I. García-Cortés et al, Fuelling efficiency of hydrocarbons in TJ-II plasmas, J. Nucl. Mat. 337-339 (2005) 441-445

[4] E. de la Cal et al, Hydrogen recycling and puffing at a poloidal limiter of TJ-II, J. Nucl. Mat. 363-365 (2007) 764-769

[5] C. Hidalgo et al, Improved confinement regimes induced by limiter biasing in the TJ-II stellarator, Plasma Phys. Control. Fusion 46 (2004) 287-297

[6] A.V. Vertkov, I.E. Lyublinski, F. Tabares, E. Ascasibar, Development of Liquid Lithium Limiter for Stellarator TJ-II, 23^rd IAEA Fusion Energy Conference, Daejon, Korea (2010) FTP/P1-34

[7] I.E. Lyublinski, A.V. Vertkov, et al., Development and experimental study of Lithium based plasma facing elements for fusion reactor application, 23^rd IAEA Fusion Energy Conference, Daejon, Korea (2010) FTP/3-6Rb

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