Keyword: plasma
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WEPD12 A Large Channel Count Multi Client Data Acquisition System for Superconducting Magnet System of SST-1 target, controls, monitoring, status 26
 
  • K.J. Doshi, J.A. Dhongde, Y.S. Khristi, H.A. Masand, B.A. Parghi, D.A. Patel, S. Pradhan, U.A. Prasad, A.N. Sharma, P.A. Varmora
    IPR, Bhat, Gandhinagar, India
 
  The magnet system of the steady-state superconducting tokamak-1 at the Institute for Plasma Research, Gandhinagar, India, consists of sixteen Toroidal field and nine poloidal field Superconducting coils together with a pair of resistive PF coils, an air core ohmic transformer and a pair of vertical field coils. These coils are instrumented with various cryogenic grade sensors and voltage taps to monitor it's operating status and health during different operational scenarios. A VME based data acquisition system with remote system architecture is implemented for data acquisition and control of the complete magnet operation. Client-Server based architecture is implemented with remote hardware configuration and continuous online/ offline monitoring. A JAVA based platform independent client application is developed for data analysis and data plotting. The server has multiple data pipeline architecture to send data to storage database, online plotting application, Numerical display screen, and run time calculation. This paper describes software architecture, design and implementation of the data acquisition system.  
poster icon Poster WEPD12 [1.959 MB]  
 
WEPD18 Microcontroller Based DAQ System for IR Thermography by Hot and Cold Water Flow LabView, controls, solenoid 37
 
  • M.S. Khan, S.M. Belsare, K.D. Galodiya, S.S. Khirwadkar, T.H. Patel
    IPR, Bhat, Gandhinagar, India
 
  There are many Non Destructive Technique used in science and industry to evaluate the properties of a material, component or system without causing damage Infrared Thermography is one of them. Different types of IR thermo-graphy are used for different purpose. We are using hot and cold-water flow IR Thermography method to evaluate the Performance of Plasma Facing Components (PFC) for Divertor Mock-up. The Set-up is designed in such a way that hot and Called Water can flow in both direction inside mockup, like left to right and right to Left using electric motor. Eight numbers of Solenoid Valves have been used for selection of Water Flow Direction, thermo-couples for temperature measurement of water, IR camera to take the images and many others devices. Which needs a very good and versatile DAC system. We have developed a DAC system usingμcontroller and LabView for the acquisition of various parameters and controlling & synchronization of other system. Development of DAC is described in this paper  
poster icon Poster WEPD18 [0.466 MB]  
 
WEPD23 Design & Implementation Of LabVIEWTM Based GUI for Remote Operation and Control of Excimer Laser for Plasma Wakefield Accelerator Experiment laser, GUI, ion, controls 46
 
  • K.K. Kizhupadath, R.A.V. Kumar, K. Mahavar
    IPR, Bhat, Gandhinagar, India
  • S. Joshi, A. Sharma
    Nirma University, Ahmedabad, India
 
  The paper describes the development of GUI based control software for control/operation, maintenance and data logging of a Coherent CompexPro 102 Excimer Laser (ArF, 193 nm) using LabVIEWTM instrument control software. Excimer laser will be used to generate the lithium plasma for the Plasma Wake Field Acceleration (PWFA) experiment which is currently being pursued at the Institute for Plasma research, Gandhinagar. The LabViewTM drivers for the system were developed and various control modules for laser control & operation, maintenance (gas refill), energy calibration as well as logging were developed and integrated into a single screen GUI. Automated calibration of the internal energy meter with an external one has also been implemented. The modules can be used independently or as an integrated system. The laser is interfaced to the control PC through a RS-232-to-USB interface.  
poster icon Poster WEPD23 [0.898 MB]  
 
THPD30 High Voltage Controller System for Spectroscopy Diagnostics of SST-1 controls, GUI, diagnostics, high-voltage 200
 
  • H.D. Mandaliya, P.V. Edappala, R. Jha, R. Rajpal, M. Shah
    IPR, Bhat, Gandhinagar, India
 
  We have developed special instrumentation for spectroscopy diagnostics of the SST-1 Tokamak. Light output in the visible spectrum is guided through fiber optics from the Tokamak ports to the diagnostics Hall, where photo multipliers tubes and other instrumentation electronics are kept. High Voltage(0 - 1500 V) bias generation electronics is required to bias these PMTs. Total 14 PMTs to be biased for overall requirements of the diagnostics. We have developed modular electronics for HV bias generation, which consist of one controller and seven HV modules. We have designed and developed FPGA based controller card which controls seven HV modules. The Slot-0 card is having Spartan 3E FPGA and Standalone Controller Area Networking (CAN) controller. 32-bit RISC processor Microblaze has been deployed into the FPGA. We have used Hitek make HV supply modules which is programmable. In the HV modules, Analog Device Inc. make iCoupler, digital isolators are used to break the ground loops and to avoid ground-lifting problem. Various features like Manual mode/Remote mode operation, HV ON/OFF, HV Value setting through remote GUI have been developed on LabVIEW software.  
 
THPD40 Instrumentation Architecture for ITER Diagnostic Neutral Beam Power Supply System controls, power-supply, ion, injection 214
 
  • A.M. Thakar, U.K. Baruah, R. Dave, H.A. Dhola, S. Gajjar, V. Gupta, D.C. Parmar, A.M. Patel, B.M. Raval, N.P. Singh
    IPR, Bhat, Gandhinagar, India
  • J.Y. Journeaux, D. Lathi, B. Schunke, S. Svensson
    ITER Organization, St. Paul lez Durance, France
 
  A Neutral Beam Injection system is used for either heating or diagnostics of the plasma in a tokamak. The Diagnostics Neutral Beam system [1] for ITER based on acceleration of negative ions; injects a neutral (Ho) beam at 100KeV with specified modulation into the plasma for charge exchange recombination spectroscopy. DNBPS system consists of HVPS, HCPS and RF Sources. The system operates in a given operating sequence; very high electromagnetic transients are intrinsically generated during operation. Instrumentation is to be provided to operate the DNBPS system remotely with required control and protection. The operation is to be synchronized with ITER operation as directed by CODAC. Instrumentation functionality includes
  1. Acquisition of injector performance parameters,
  2. Operation and control of necessary auxiliaries,
  3. Protection of DNB components and power supplies using interlock system,
  4. To ensure safe operation of high voltage hazardous systems and
  5. To facilitate test and maintenance of individual subsystem.
This paper discusses about proposed DNB instrumentation architecture. The design generally follows the protocols from the ITER- Plant Control Design Handbook.

[1] Lennart Svensson et.al, "Instrumentation and diagnostics for the ITER Neutral Beam System", Fusion Engineering and Design 86 (2011)
 
poster icon Poster THPD40 [1.032 MB]