DocumentCode :
1434942
Title :
SST-1 Status and Plans
Author :
Pradhan, Subrata ; Sharma, Aashoo N. ; Tanna, Vipul L. ; ZKhan, Z. ; Prasad, Upendra ; Doshi, Kalpesh ; Raval, Dilip C. ; Khan, Ziauddin ; Gupta, Naresh C. ; Tank, Jignesh ; Gupta, Manoj K. ; Santra, Prosenjit ; Biswas, Prabal ; Parekh, Tejas ; Masand, Ha
Author_Institution :
Inst. for Plasma Res., Gandhinagar, India
Volume :
40
Issue :
3
fYear :
2012
fDate :
3/1/2012 12:00:00 AM
Firstpage :
614
Lastpage :
621
Abstract :
The Steady State Superconducting 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 January 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, ensuring thermal and electrical isolations between various subsystems of SST-1, testing of each of the SST-1 toroidal field (TF) magnets at 4.5 K with nominal currents, testing each of the modules and octants of the SST-1 machine shell in representative experimentally simulated scenarios, augmentation and reliability establishment of the SST-1 vacuum vessel baking system, time synchronizations among various heterogeneous subsystems of SST-1, large data-storage scenarios, and integrated engineering testing of the first phase of the plasma diagnostics 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 poloidal field magnets began in December 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-seconds and could possibly be assisted by ECCD/LHCD.
Keywords :
Tokamak devices; machine windings; plasma diagnostics; plasma toroidal confinement; superconducting machines; SST-1 machine shell; SST-1 mission mandate; SST-1 superconducting magnet system; SST-1 vacuum vessel baking system; augmentation; cold test; electrical isolation; heterogeneous subsystems; integrated engineering testing; large data-storage scenarios; magnet winding packs; nominal currents; octants; plasma diagnostics; poloidal field magnets; refurbishment activities; reliability; single-phased LN<;sub>;2<;/sub>;-cooled thermal shields; steady state superconducting tokamak; subnano-ohm leak-tight joints; supercritical-helium-cooled 5-K thermal shields; temperature 4.5 K; thermal isolation; time synchronizations; Helium; Joints; Magnetic noise; Magnetic shielding; Plasmas; Superconducting magnets; Toroidal magnetic fields; Baking; Steady State Superconducting Tokamak (SST-1); bubble shields; leak-tight sub-nano-ohm dc joint resistance and first plasma; supercritical helium;
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2011.2179678
Filename :
6142113
Link To Document :
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