Instrumentation Architecture for ITER Diagnostic Neutral Beam … · 2013-05-30 · arch D N wit h...

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INSTRUMENTATION ARCHITECTURE FOR ITER DIAGNOSTIC NEUTRAL BEAM POWER SUPPLY SYSTEM A. Thakar, H. Dhola, R. Dave, N.P. Singh, B. Raval, D. Parmar, A. Patel, S. Gajjar, V. Gupta, U. Baruah,ITER-India, IPR, Gandhinagar, India L. Svensson, J.Y. Journeaux, D. Lathi, B. Schunke ITER Organisation, St Paul Lez Durance, France Abstract A Neutral Beam (NB) Injection system is used for heating or diagnostics of the plasma in a Tokamak. The Diagnostics Neutral Beam (DNB) system for ITER (International Thermonuclear Experimental Reactor) based on acceleration of negative ions; injects a neutral (H˳) beam at 100keV with specified modulation into the plasma for charge exchange recombination spectroscopy. DNB Power Supply (DNBPS) system consists of various high voltage power supplies, high current power supplies and RF Generators. The system operates in a given operating sequence; very high electromagnetic transients are intrinsically generated during frequent short circuit at the accelerator grid (breakdowns) and sudden loss of load (Beam off). Instrumentation is to be provided to operate the DNBPS system remotely with required control and protection in synchronisation with ITER operation as directed by CODAC (COntrol Data Access and Communication); the central control system for ITER. Instrumentation functionality includes 1.Operation and control of DNBPS subsystems and associated auxiliaries 2.Protection of DNB components and power supplies using interlock system, 3.To ensure safe operation of high voltage hazardous systems 4. Acquisition of injector performance parameters and 5.To facilitate test and maintenance of individual subsystem. This paper discusses about proposed DNBPS instrumentation architecture. The design generally follows the protocols from the ITER- Plant Control Design Handbook (PCDH). INTRODUCTION The DNB Power Supply system [1,2 , ] feeds the required controllable electrical power to the DNB beam source (BS), the Residual Ion Dump (RID) and the Active Correction and Compensation coils (ACCC). The system comprises of various high voltage, High Current power supplies and RF generators for plasma generation in the ion source, with integrated controllers. Table 1: DNBPS Main Subsystems, their control, monitoring and protection parameters Sub Systems Controlling parameter Measurements Protection events Acceleration Grid PS (AGPS) 96kV, 75A Voltage, Modulation Voltage, Current, Cooling water parameters Breakdown, Beam off, Failure in RID voltage, Short circuit at power supply end Extractor Grid Power Supply (EGPS) 12kV, 140A Voltage, Modulation Voltage, Current , Cooling water parameters Breakdown, Beam off, Short circuit at power supply end Residual Ion Dump Power supply (RIDPS) 8kV, 60A Voltage, Operation time Voltage, Current, Cooling water parameters Short circuit RF Generators 4 X 200kW Frequency, RF power, Modulation Frequency, Phase, Power, Cooling water parameters Break down, Beam off (Reduce RF power to notch level) Active Correction Coil Power Supply (ACCPS) 1.4kV, 440A Current Current, Magnetic field around DNB cell, Cooling water parameters Short circuit protection Plasma Grid Bias Power Supply ; 30V, 600A Current, Voltage Current, Voltage, Cooling water parameters Short circuit protection Plasma Grid Filter Power Supply;15V, 4kA Current, Voltage Current, Voltage, Cooling water parameters Short circuit protection Cs oven Shutter control, Temperature Temperature - THPD40 Proceedings of PCaPAC2012, Kolkata, India ISBN 978-3-95450-124-3 214 Copyright c 2012 by the respective authors Status Report/Overview of Control System

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INSTRUMENTATION ARCHITECTURE FOR ITER DIAGNOSTIC NEUTRAL BEAM POWER SUPPLY SYSTEM

A. Thakar, H. Dhola, R. Dave, N.P. Singh, B. Raval, D. Parmar, A. Patel, S. Gajjar, V. Gupta, U. Baruah,ITER-India, IPR, Gandhinagar, India

L. Svensson, J.Y. Journeaux, D. Lathi, B. Schunke ITER Organisation, St Paul Lez Durance, France

Abstract

A Neutral Beam (NB) Injection system is used for heating or diagnostics of the plasma in a Tokamak. The Diagnostics Neutral Beam (DNB) system for ITER (International Thermonuclear Experimental Reactor) based on acceleration of negative ions; injects a neutral (H˳) beam at 100keV with specified modulation into the plasma for charge exchange recombination spectroscopy. DNB Power Supply (DNBPS) system consists of various high voltage power supplies, high current power supplies and RF Generators. The system operates in a given operating sequence; very high electromagnetic transients are intrinsically generated during frequent short circuit at the accelerator grid (breakdowns) and sudden loss of load (Beam off).

Instrumentation is to be provided to operate the DNBPS system remotely with required control and protection in synchronisation with ITER operation as directed by CODAC (COntrol Data Access and Communication); the central control system for ITER. Instrumentation functionality includes 1.Operation and control of DNBPS

subsystems and associated auxiliaries 2.Protection of DNB components and power supplies using interlock system, 3.To ensure safe operation of high voltage hazardous systems 4. Acquisition of injector performance parameters and 5.To facilitate test and maintenance of individual subsystem.

This paper discusses about proposed DNBPS instrumentation architecture. The design generally follows the protocols from the ITER- Plant Control Design Handbook (PCDH).

INTRODUCTION The DNB P ower S upply s ystem [ 1,2, ] f eeds the required

controllable electrical power to the DNB beam source (BS), the Residual Ion Dump (RID) and the Active Correction and Compensation coils (ACCC). The system comprises of various high voltage, High Current power supplies and RF generators for plasma generation in the ion source, with integrated controllers.

Table 1: DNBPS Main Subsystems, their control, monitoring and protection parameters

Sub Systems Controlling parameter

Measurements Protection events

Acceleration Grid PS (AGPS)

96kV, 75A

Voltage, Modulation

Voltage, Current, Cooling water parameters

Breakdown, Beam off, Failure in RID voltage, Short circuit at power supply end

Extractor Grid Power Supply (EGPS)

12kV, 140A

Voltage, Modulation

Voltage, Current , Cooling water parameters

Breakdown, Beam off, Short circuit at power supply end

Residual Ion Dump Power supply (RIDPS)

8kV, 60A

Voltage, Operation time

Voltage, Current, Cooling water parameters

Short circuit

RF Generators

4 X 200kW

Frequency, RF power, Modulation

Frequency, Phase, Power, Cooling water parameters

Break down, Beam off (Reduce RF power to notch level)

Active Correction Coil Power Supply (ACCPS)

1.4kV, 440A

Current Current, Magnetic field around DNB cell, Cooling water parameters

Short circuit protection

Plasma Grid Bias Power Supply ; 30V, 600A

Current, Voltage

Current, Voltage, Cooling water parameters

Short circuit protection

Plasma Grid Filter Power Supply;15V, 4kA

Current, Voltage

Current, Voltage, Cooling water parameters

Short circuit protection

Cs oven Shutter control, Temperature

Temperature -

THPD40 Proceedings of PCaPAC2012, Kolkata, India

ISBN 978-3-95450-124-3

214Cop

yrig

htc ○

2012

byth

ere

spec

tive

auth

ors

Status Report/Overview of Control System

Page 2: Instrumentation Architecture for ITER Diagnostic Neutral Beam … · 2013-05-30 · arch D N wit h lanoitcn uCf and auxiliari e To start beam a predefined s During opera ... info

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Status Report/Overview of Control System

ISBN 978-3-95450-124-3

215 Cop

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2012

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THPD40 Proceedings of PCaPAC2012, Kolkata, India

ISBN 978-3-95450-124-3

216Cop

yrig

htc ○

2012

byth

ere

spec

tive

auth

ors

Status Report/Overview of Control System