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
Link To Document :
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