TJ-II:Limiter

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TJ-II has two mobile limiters, located in sectors A3 and C3 (105.5º 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

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, 23rd 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, 23rd IAEA Fusion Energy Conference, Daejon, Korea (2010) FTP/3-6Rb
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