• DocumentCode
    1950566
  • Title

    SST-1status & plans

  • Author

    Pradhan, S. ; Sharma, A.N. ; Tanna, V.L. ; Khan, Ziauddin ; Prasad, U. ; Raval, D.C. ; Khan, Firoz ; Gupta, N.C. ; Tank, J. ; Gupta, M.K. ; Santra, P. ; Biswas, P. ; Masand, H. ; Sharma, D. ; Srivastava, A. ; Patel, H.

  • Author_Institution
    Inst. for Plasma Res., Gandhinagar, India
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    7
  • Abstract
    Steady State Tokamak (SST-1) is currently being refurbished in a mission mode at the Institute for Plasma Research with an ultimate objective of producing the first plasma in early 2012. Since Jan 2009, under the SST-1 Mission mandate, a broad spectrum of refurbishment activities have been initiated and pursued on several subsystems of SST-1. Developing sub nano-ohm leak tight joints in the magnet winding packs, developing single phased LN2 cooled thermal shields, developing supercritical helium cooled 5 K thermal shields for magnet cases, insurance of thermal and electrical isolations between various sub-systems of SST-1, testing of each of the SST-1 Toroidal Field (TF) magnets in cold with nominal currents, testing each of the modules and octants of SST-1 machine shell in representative experimentally simulated scenarios, augmentation and reliability establishment of the SST-1 vacuum vessel baking system, time synchronizations amongst various heterogeneous subsystems of SST-1, large data storage scenarios, integrated engineering testing of the first phase of the plasma diagnostics etc are some of the major refurbishment activities. Presently, the SST-1 device integration is in full swing. The cold test of the assembled SST-1 TF and PF magnets are due to begin from Dec 2011. Following the successful testing of the SST-1 superconducting magnet system and engineering validations of the machine shell, the first plasmas will be attempted in SST-1. The first plasma will be ~ 100 kA limiter assisted with the available volt-sec and could possibly be assisted by ECCD/LHCD.
  • Keywords
    Tokamak devices; plasma diagnostics; AD 2012; ECCD/LHCD; Institute for Plasma Research; SST-1; Steady State Tokamak; data storage scenarios; integrated engineering testing; magnet cases; magnet winding packs; mission mode; plasma diagnostics; refurbishment activities; single phased LN2 cooled thermal shields; sub nano-ohm leak tight joints; superconducting magnet system; supercritical helium cooled 5 K thermal shields; time synchronizations; Coils; Cryogenics; Heating; Hydrogen; Reliability; Tokamaks; Windings; Baking; Bubble shields; Leak tight sub-nΩ DC joint resistance and first plasma; SST-1 Tokamak; supercritical helium;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052353
  • Filename
    6052353