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"The Li-CPS Plasma Face Components for steady-state tokamak experiment“ S. Mirnov

"The Li-CPS Plasma Face Components for steady-state tokamak experiment“ S. Mirnov TRINITI Troitsk Moscow Reg. 2003. LI 7 characteristics. Specific weight ( g/cm 3 ) - 0,5 Electric conductivity ( ohm cm ) -1 - 2,2 10 4 

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"The Li-CPS Plasma Face Components for steady-state tokamak experiment“ S. Mirnov

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  1. "The Li-CPS Plasma Face Components for steady-state tokamak experiment“ S. Mirnov TRINITI Troitsk Moscow Reg. 2003

  2. LI7 characteristics • Specific weight (g/cm3) - 0,5 • Electric conductivity (ohm cm)-1 - 2,2 104  • Heat conductivity (W/cm grade) - 0,43 (1830С) - 0,53 (6270С) • Heat capacity (kal/cm3grade) - 0,5 • Melting temperature - 180,50С • Evaporation temperature- 13170С • Evaporation heat (eV/at) - 1,5 • Energetic “price” of Li+++ ionized by electrons with Те=30eV (eV/at) -1200 • Temperature range of D, T recovery -320-5000С

  3. Tritium recovery • V.A. Evtikhin et al. Fus. Eng. Design 56-57 (2001),p.363 • M. J. Baldwin et al. 43 An. Meeting APS, Divis. Plasma Phys.(2001) Rep. N CP1 25. • Y. Furuyama et al. 15 PSI Conf. 2002 J. Nucl. Mat. 313-316 p.288

  4. Li Capillary Porous Structures

  5. Li Divertor Concept

  6. T- 11M Li- experiment

  7. The radial radiation distribution in experiments with C and Li limiters

  8. Lithium flux (erosion) from 200 to 650 C

  9. Summary (1) 1.Lithium, as lowZ-material, is compatible with tokamak plasma (TFTR, T-11M, CDXU). 2.The surface tension forces in CPS may be used to solve the problem of ponderomotive forces (splashing suppress) and regeneration problem of PFC.

  10. Summary (2) 3.Experiments with hydrogen (deuterium) and helium plasmas on T-11M tokamak with Li – CPS limiter have shown: -No spontaneous bursts of lithium ejection under heat flux to limiter at the level about 10 MW/m2 have been observed. -Total lithium erosion close to level of hydrogen and lithium ions sputtering has been measured. - The lithium radiation protected the limiter from high power load during disruptions. -The solid basis of CPS limiter had no damages after more than 2103 of plasma shots. -The recovery temperature of hydrogen isotopes from Li is 320-500oC (for helium 50-100oC). Therefore, at high PFC temperatures (4000-5000 C) a tritium capture can be minimized. -It should be provided, that separation of helium and hydrogen isotopes will be possible in lithium circuit with lower PFC temperatures.

  11. Summary (3) 4.These results are making a convincing basis for the advance of the liquid lithium PFC for steady state tokamak. The following problems of such tokamak might be decided: - wall and divertor plates erosion, - “dust” accumulation and redeposition, - tritium recovery, - low Zeff(0), - heat removal in stationary conditions and during disruptions.

  12. Summary (4) 5.The progress of the considered approach needs further experimental, calculation, design research and technological developments. The following studies seem necessary: - experiments with lithium in divertor tokamaks, - calculations of lithium behavior in divertor region and SOL on the basis of existing codes, including evaporation, condensation, ionization processes etc.

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