• DocumentCode
    1059179
  • Title

    Hydraulics of KSTAR Central Solenoid Model Coil 2nd Campaign

  • Author

    Park, Soo Hwan ; Han, W.S. ; Moon, K.M. ; Park, W.W. ; Kim, J.S. ; Yonekawa, Hirofumi ; Chu, Yong ; Lee, Hyun Jung ; Cho, K.W. ; Park, K.R. ; Kim, W.C. ; Kim, Yaung-Soo ; Oh, Y.K. ; Bak, J.S.

  • Author_Institution
    Nat. Fusion Res. Inst., Daejeon, South Korea
  • Volume
    19
  • Issue
    3
  • fYear
    2009
  • fDate
    6/1/2009 12:00:00 AM
  • Firstpage
    1569
  • Lastpage
    1572
  • Abstract
    KSTAR (Korea Superconducting Tokamak Advanced Research) superconducting magnet consists of a CICC (Cable-In-Conduit Conductor) and is cooled down less than 5 K using supercritical helium. The length of CICC is 610 m for TF coil and maximum about 2,500 m for PF coil respectively, especially the cooling channel is about maximum 300 m in PF coil because of continuous winding scheme. There are many cooling channels in KSTAR coils especially 84 channels in TF magnet system and 100 channels in PF magnet system. Flow imbalance affects cool down of magnet and leads to a difficulty of flow control. The pressure drop between CICC terminals has a close relationship with CICC hydraulic characteristic, helium refrigerator´s performance and efficiency. The friction factor which is a representative parameter can be obtained under cryogenic operation condition. We attempt to find out the friction factor of KSTAR CS and PF CICC according to the test result of KSTAR CSMC (Central Solenoid Model Coil) 2nd campaign and compare the results with previous tests. The hydraulic characteristics of KSTAR superconducting magnet system like mass flow distribution, friction factor in conductor, pressure drop and etc during CSMC test and initial commissioning of KSTAR are presented. We can confirm the KSTAR CICC´s unique hydraulic behavior in states of cool down and current charging period. Also, we expect that measured data will help to operate KSTAR and be a reference for thermo-hydraulic simulation.
  • Keywords
    Tokamak devices; channel flow; cryogenics; fusion reactor materials; fusion reactor operation; niobium alloys; plasma toroidal confinement; superconducting coils; superconducting magnets; tin alloys; CICC; CSMC; Cable-In-Conduit Conductor; ITER; KSTAR; Korea Superconducting Tokamak Advanced Research; Nb3Sn; PF coil; TF coil; TF magnet system; central solenoid model coil; cooling channels; cryogenic operation; flow imbalance affects; friction factor; fusion devices; helium refrigerator; hydraulic characteristic; mass flow distribution; size 610 m; superconducting magnet system; supercritical helium; thermo-hydraulic simulation; winding scheme; CSMC; KSTAR; hydraulics; superconducting magnets;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2009.2018485
  • Filename
    5067063