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28/29 October 2008Colloquium on ITER-CODAC1 Examples of ITER CODAC requirements for diagnostics S. Arshad Colloquium on ITER-CODAC Plant Control Design.

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Presentation on theme: "28/29 October 2008Colloquium on ITER-CODAC1 Examples of ITER CODAC requirements for diagnostics S. Arshad Colloquium on ITER-CODAC Plant Control Design."— Presentation transcript:

1 28/29 October 2008Colloquium on ITER-CODAC1 Examples of ITER CODAC requirements for diagnostics S. Arshad Colloquium on ITER-CODAC Plant Control Design Handbook and EU Procurement of Control and Instrumentation for ITER 28 October 2008

2 28/29 October 2008Colloquium on ITER-CODAC2 Hot fusion plasma can be contained in a magnetic field

3 28/29 October 2008Colloquium on ITER-CODAC3 JET: Worlds largest tokamak ITER R (m)6.2 a (m)2 I P (MA)16 B t (T)5.3 P aux (MW)40 – 90 P (MW)80+ Q (P fus /P in )10 P rad (MW)48 t pulse (s)400+ R a New engineering and physics challenges for measurement and control Containment improves with size – ITER will be much larger than todays machines

4 28/29 October 2008Colloquium on ITER-CODAC4 UPPER PORT 11 Edge Thomson UPPER PORT 10 X-Ray Survey Imaging VUV Spectroscopy EQUATORIAL PORT 9 MSE Toroidal Interferometer / Polarimeter ECE Wide Angle TV/IR Port type EQUATORIAL PORT 11 X-Ray Crystal Spectroscopy, array Divertor VUV Spectroscopy X-Ray Survey Core VUV Monitor Neutral Particle Analyser Reflectometry DIVERTOR PORT 8 Divertor Reflectometry DIVERTOR PORT 10 X-point LIDAR Divertor Thomson Scattering H-Alpha Spectroscopy Wide range of diagnostics needed to diagnose fusion plasma No. used Equatorial9 Upper12 Lower9 Additionally many measurements inside vessel

5 28/29 October 2008Colloquium on ITER-CODAC5 The EU will supply a range of diagnostics to ITER Analog processing ADC Off-line processing Real-time processing Controller Machine protection & plasma control Physics studies Ports for diagnostics & heating systems General scheme for processing of diagnostic data Processed data from diagnostics (Courtesy of EFDA-JET) Plasma shape & neutron profile Plasma wall interaction Temperature & density profiles Wide-angle viewing system Magnetics Radial neutron camera Core Thomson scattering Bolometers Core charge exchange recombination spectrometer Hard X-ray monitor Plasma position reflectometer Pressure gauges Thermocouples LFS collective Thomson scattering High-resolution neutron spectrometer Gamma-ray spectrometers About 40 diagnostic systems installed in ports and inside / outside the toroidal chamber; 13 to be supplied by the EU:

6 28/29 October 2008Colloquium on ITER-CODAC6 The magnetics diagnostic is a large system for basic plasma control, machine protection and physics studies Diagnostic comprises pick-up coils, flux loops, Rogowski coils ~1050 sensors inside the vessel (shown in figure) ~600 additional sensors outside vessel In-vessel pick-up coil Ex-vessel pick-up coil External rogowski coil PurposePrototype magnetics sensors Determine plasma current, shape and movement Measure thermal energy of plasma Detect and quantify plasma instabilities Reconstruct magnetic flux surfaces (equilibrium) Detect and quantify any current flowing from plasma into vessel ControlProtectionPhysics Hall probe

7 28/29 October 2008Colloquium on ITER-CODAC7 Overview of magnetics signal processing Around 1650 sensors in total Digital or analogue integrators Amplifiers Slow (4kHz) ADCs for basic equilibrium Fast (1 MHz) ADCs for instabilities Typically with optical isolation Data stored for specialist off-line studies Real-time signals distributed to other plant systems (power amplifiers for tokamak magnets, machine protection systems) Event triggers Off-line processing Real-time processing Physics studies Control & protection dB/dt B Int Amp ADC ALL NUMBERS ARE INDICATIVE

8 28/29 October 2008Colloquium on ITER-CODAC8 Plasma current and shape (1/2) Plasma current measured by integrating magnetic field over poloidal contour (Amperes law) Plasma shape characterised by gap between plasma boundary (solid red line) and first wall Shape controlled by changing current in tokamak coils

9 28/29 October 2008Colloquium on ITER-CODAC9 Plasma current and shape Event triggers ADC Off-line processing Real-time processing Physics studies Control & protection dB/dt B Around 750 sensors (of which 380 in- vessel) Typical raw signal from 0.05m 2 pick-up coil in +/-60mV range under normal operation; +/-5V at disruptions Individual signals integrated (typical time constant 100ms; output +/-5V) and digitised separately Integrated signal in range of 0.06Vs; frequency response ~10kHz; drift <0.35mVs after pulse of 3600s Summing integrator for hardware calculation of plasma current (10kA-15MA range, 1% accuracy) Integrated signals typically sampled at 4kHz (20kHz at events) Typically 16 bit ADC with dithering, 25 bits without) Calibration of signals On-line data validation checks and corrective actions (e.g. voting system with 3 toroidal positions) Second plasma current calculation from individual signals Plasma boundary and plasma-wall gaps determined (1-2cm accuracy) 100k FLOP/cycle (10ms cycle time 0.01GFLOPS) Control signals generated for gap control and distributed to power amplifiers for tokamak coils Data stored for specialist off-line studies including full equilibrium reconstruction combining data from other diagnostics (20GB per pulse) Int Amp Similar arrangement for 410 in-vessel Rogowski coils feeding vessel current reconstruction code ALL NUMBERS ARE INDICATIVE

10 28/29 October 2008Colloquium on ITER-CODAC10 High frequency instabilities – analysis & control Around 270 high frequency sensors (with response up to 100kHz) High frequency results in relatively strong (voltage- range) signals which can be recorded directly with low gain Frequency response up to 300kHz RMS signals from summing amplifiers may for rapid overview of instabilities or for event triggering 16 bit resolution likely to be adequate Sampling rates up to 1 MHz Event triggering to manage data quantities Data stored for specialist off-line studies; of order 50GB per pulse Real-time signals for feedback control (resistive-wall modes) Additional, more specialised, event triggers Event triggers Off-line processing Real-time processing Physics studies Control & protection dB/dt B Int Amp Similar arrangement for around 380 in-vessel sensors for plasma vertical speed control; 10kHz sampling; 30GB storage; 1GFLOPS ADC ALL NUMBERS ARE INDICATIVE

11 28/29 October 2008Colloquium on ITER-CODAC11 Overview of requirements for some diagnostics SystemElectronicsADCsStorage (per pulse) Magnetics1200 integrators 650 amplifiers 1600 slow ADC channels (20kHz) 270 fast ADC channels (1 MHz) 110GB Bolometry500 lock-in amplifiers (50kHz) 500 ADC channels 360MB Charge Exchange Read-out from up to 75 CCD cameras (100 spectra/sec. 560 pixels each) N/A30GB Core LIDAR TS 150 ADC channels at 20GSa/S; 10-bit samples 100MB ALL NUMBERS ARE INDICATIVE


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