1
Shape Controller Upgrades for the JET ITER-like Wall This work was supported by the European Communities under the contract of Association between EURATOM/IST and was carried out within the framework of the European Fusion Development Agreement. See the Appendix of F. Romanelli et al., Proceedings of the 23rd IAEA Fusion Energy Conference 2010, Daejeon, Korea. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Shape Controller Execution sequence Data Acquisition Data Processing Magnetic Boundary Reconstruction Control Mode Selection Reference Generation eXtreme Shape Controller Current Limit Avoidance Sweeping Module Main Controller Run internal Diagnostics Output Data Shared memory buffer Real-time network Analogue Digital Clock & time Real-time network Analogue Digital JET Circuits Circuit name Toroidal Field Magnetising Vertical Field Fast Radial Field Radial Field X-Point Shaping Divertors (TF) (P1) (P4T) (RFA) (IMB) (PFX) (SHA) (D1-4) Coils series 24 toroidal coils P3MU/L+P1EU/L+P1C P4U+P4L P2/3RU-P2/3RL P4U-P4L P1C P2SU/L+P3SU/L D1, D2, D3, D4 P2RU • Real-time system ~~MIMO controller • Controls: ~~current in poloidal field circuits ~~plasma current ~~plasma shape Plasma Position Current Controller Shape Controller Poloidal Field Circuits Magnetics Data Acquisition Plasma Protection Systems Volts Current Magnetic measurements Overview Architecture Processor O.S. Inputs Outputs Cycle time VME MVME5100 PowerPC VxWorks 48 ADCs 2 Digital inputs >400 ATM signals 24 DACs 1 Digital output >150 ATM signals 2 ms P1 P4T P4I PFX SHA D1 D2 D3 D4 Block Block Block Block Block Block Block Block V=0 Block Block Block Block Block Block Current Current Current Current Ip Gap Current Current Current Current Current Current Ip Gap Current Current Current Current Gap Gap Gap Ip t 0 t 1 t 2 t N t N+1 t 25 Control modes and values dynamically assigned -Pre-programmed time windows -Stopping event Control mode selection • 10 Poloidal field circuits ~~9 controlled by shape controller • First line of defence against faults and limits implemented in SC Ip Ip Gap Current Current Current Current Gap Gap Gap Ip Gap Current Current Current Current Gap Gap Gap Ip Gap Current Current Current Current Gap Gap Gap P1 P4T P4I PFX SHA D1 D2 D3 D4 Block Block Block Block Block Block Block Block V=0 Block Block Block Block Block Block Current Current Current Current Ip Gap Current Current Current Current Current Current Ip Gap Current Current Current Current Gap Gap Gap Ip t 0 t 1 t 2 t N t N+1 t 25 Protection of the ITER Like Wall (PIW) Stopping Strategy • JET upgraded to a new all metal wall • Previously, upon the detection of a problem: ~~Set of global responses ~~~Invariant with the experimental phase ~~~Designed to maximise the likelihood of a safe plasma landing ~~ Might conflict with the requirement of avoiding localised heat fluxes in the wall components Upgraded system capable of dynamically adapting its response behaviour: ~~Accordingly to the experimental conditions at the time of the stop request ~~During the termination itself • Capable of switching to alternative experiment sequence if resources not available • Triggered by the new Real-time Protection Sequencer (RTPS) ~~ Responds to alarm requests from the Vessel Thermal Map (VTM) ~~ Communicates using the ATM real-time data network Real-time Protection Sequencer (RTPS-PIW) Pulse Termination Network (PTN-pre-PIW) JET Central Timing RTPS Time Control Logic Shape Controller Vessel Thermal Map (VTM-PIW) PTN Digital IO ATM ATM Digital IO Infrared cameras & Pyrometers ATM PFX On Early Task (POET) Current Limit Avoidance 0 0 40 -40 -40 40 IP1E (kA) IP1C (kA) Example of plasma pulse trajectory Interlock limit Maximum PFX in POET Any current in PFX No current in PFX Limited current in PFX S1b PFX S1a S4a S4b R3a R3b R4a R4b P PFGC P1 coil IP1C IP1E • PFGC P1E generates and controls plasma current ~~400 MW fly-wheel generator ~~Hardware swichtes (s1 and s4) enable current in both directions PFX drives current in central pancakes windings ~~Reduce stray fields ~~More D shaped plasma • Current in PFX inhibited by shape controller... ~~...while current in P1E is of opposite sign • Electromechanical modelling effort concluded that the old limits are too stringent POET operation space allows limited PFX current with P1E current in the opposite direction SC (set to prop. current control) PF Circuits V Plasma Measured currents Shape reconstruction algorithm Magnetics data acquisition system CLA XSC Shape Ref. + - Measured Shape Additional shape references I Ref. Shape Ref. + - I Ref. + - IP1C = IP1E + IPFX • Control logic upgraded to open 3 operational regions ~~Logic protects and tracks wrong requests • Early operation of PFX enables ~~Longer pulse length in the X-point plasma configuration, where the plasma last closed surface is • eXtreme Shape Controller (XSC) algorithm enables the control of the full plasma boundary ~~system is no longer limited to the accurate control of only a few gaps ~~all the circuits in shape controller are set to proportional current control ~~current references provided by the XSC algorithm. ~~algorithm is valid only around a given equilibrium ~~~plasma must be driven into the reference conditions using shape controller • Current Limit Avoidance (CLA) uses the redundancy of the PF coil system ~automatically obtains almost the same plasma reference shape ~~with a different combination of currents in the PF coils ~~in the presence of severe disturbances ~~~tries to avoid the current saturations ~~~by relaxing the plasma shape constraints A. Neto, P. J. Lomas, F. Maviglia, D. Alves, I. S. Carvalho, G. De Tommasi, R. Felton, P. McCullen, V. Riccardo, F. G. Rimini, A. Stephen, R. Vitelli, K-D. Zastrow 1 2 1 1 2 3 3 2 2 2 4 2 2 JET-EFDA, Culham Science Centre, OX14 3DB, Abingdon, UK 1 Associação Euratom-IST, Instituto de Plasmas e Fusão Nuclear - Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, P1049-001 Lisboa, Portugal 2 EURATOM-CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3EA, United Kingdom 3 Associazione EURATOM/ENEA/CREATE, Università di Napoli Federico II, 80138 Napoli, Italy 4 Dipartimento di Informatica, Sistemi e Produzione, Università di Roma “Tor Vergata,” 00133 Rome, Italy [email protected]

Shape Controller Upgrades for the JET ITER-like Wallepaper.kek.jp/icalepcs2011/posters/mopmu035_poster.pdf · Magnetising Vertical Field Fast Radial Field Radial Field X-Point Shaping

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Page 1: Shape Controller Upgrades for the JET ITER-like Wallepaper.kek.jp/icalepcs2011/posters/mopmu035_poster.pdf · Magnetising Vertical Field Fast Radial Field Radial Field X-Point Shaping

Shape Controller Upgrades for the JET ITER-like Wall

This work was supported by the European Communities under the contract of Association between EURATOM/IST and was carried out within the framework of the European Fusion Development Agreement. See the Appendix of F. Romanelli et al., Proceedings of the 23rd IAEA Fusion Energy Conference 2010, Daejeon, Korea. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Shape Controller

Execution sequence

DataAcquisition

DataProcessing

MagneticBoundaryReconstruction

ControlMode Selection

ReferenceGeneration

eXtremeShapeController

CurrentLimit Avoidance

SweepingModule

MainController

Run internalDiagnostics

OutputData

Shared memory buffer

Real-time network

AnalogueDigital

Clock & time

Real-time network

AnalogueDigital

JET Circuits

Circuit nameToroidal FieldMagnetisingVertical FieldFast Radial FieldRadial FieldX-PointShapingDivertors

(TF)(P1)(P4T)(RFA)(IMB)(PFX)(SHA)(D1-4)

Coils series24 toroidal coilsP3MU/L+P1EU/L+P1CP4U+P4LP2/3RU-P2/3RLP4U-P4LP1CP2SU/L+P3SU/LD1, D2, D3, D4

P2RU

• Real-time system~~MIMO controller• Controls: ~~current in poloidal field circuits~~plasma current~~plasma shape

Plasma PositionCurrent ControllerShape Controller

Poloidal FieldCircuits

MagneticsData Acquisition

Plasma

ProtectionSystems

Volts

Current

Magnetic measurements

Overview

ArchitectureProcessor

O.S.Inputs

Outputs

Cycle time

VMEMVME5100 PowerPCVxWorks48 ADCs2 Digital inputs>400 ATM signals24 DACs1 Digital output>150 ATM signals2 ms

P1

P4T

P4I

PFX

SHA

D1

D2

D3

D4

Block

Block

Block

Block

Block

Block

Block

Block

V=0

Block

Block

Block

Block

Block

Block

Current

Current

Current Current

Ip

Gap

Current

Current

Current

Current

Current

Current

Ip

Gap

Current

Current

Current

Current

Gap

Gap

Gap

Ip

t0

t1

t2

tN

tN+1 t

25

•Control modes and values dynamically assigned -Pre-programmed time windows-Stopping event

Control mode selection

• 10 Poloidal field circuits~~9 controlled by shape controller• First line of defence against faults and limits implemented in SC

Ip

Ip

Gap

Current

Current

Current

Current

Gap

Gap

Gap

Ip

Gap

Current

Current

Current

Current

Gap

Gap

Gap

Ip

Gap

Current

Current

Current

Current

Gap

Gap

Gap

P1

P4T

P4I

PFX

SHA

D1

D2

D3

D4

Block

Block

Block

Block

Block

Block

Block

Block

V=0

Block

Block

Block

Block

Block

Block

Current

Current

Current Current

Ip

Gap

Current

Current

Current

Current

Current

Current

Ip

Gap

Current

Current

Current

Current

Gap

Gap

Gap

Ip

t0

t1

t2

tN

tN+1

t25

Protection of the ITER Like Wall (PIW) Stopping Strategy

• JET upgraded to a new all metal wall• Previously, upon the detection of a problem:~~Set of global responses~~~Invariant with the experimental phase~~~Designed to maximise the likelihood of a safe plasma landing~~ Might conflict with the requirement of avoiding localised heat fluxes in the wall components• Upgraded system capable of dynamically adapting its response behaviour:~~Accordingly to the experimental conditions at the time of the stop request~~During the termination itself• Capable of switching to alternative experiment sequence if resources not available• Triggered by the new Real-time Protection Sequencer (RTPS)~~ Responds to alarm requests from the Vessel Thermal Map (VTM)~~ Communicates using the ATM real-time data network

Real-time ProtectionSequencer

(RTPS-PIW)

Pulse Termination

Network(PTN-pre-PIW)

JETCentralTiming

RTPS

Time

Control Logic

Shape Controller

VesselThermal

Map(VTM-PIW)

PTN

Dig

ital I

O

ATMATM

Digital IO

Infraredcameras

&Pyrometers

ATM

PFX On Early Task (POET)

Current Limit Avoidance

0

0

40-40-40

40

IP1E (kA)

IP1C (kA)

Example of plasma pulse trajectory

Interlock limit

Maximum PFX in POETAny current in PFX

No current in PFX

Limited current in PFX

S1b

PFX

S1a

S4a

S4b

R3a

R3b

R4a

R4bP

PFGC

P1 coil

IP1C

IP1E

• PFGC P1E generates and controls plasma current~~400 MW fly-wheel generator~~Hardware swichtes (s1 and s4) enable current in both directions• PFX drives current in central pancakes windings~~Reduce stray fields~~More D shaped plasma• Current in PFX inhibited by shape controller...~~...while current in P1E is of opposite sign• Electromechanical modelling effort concluded that the old limits are too stringent• POET operation space allows limited PFX current with P1Ecurrent in the opposite direction

SC(set to prop.

current control)

PFCircuits

VPlasma

Measured currents

Shape reconstruction

algorithm

Magnetics data acquisition system

CLAXSC

ShapeRef.

+

-

Measured Shape

Additional shape references

IRef.

ShapeRef.

+

-

IRef.+

-

• IP1C = IP1E + IPFX• Control logic upgraded to open 3 operational regions~~Logic protects and tracks wrong requests• Early operation of PFX enables~~Longer pulse length in the X-point plasma configuration, where the plasma last closed surface is

• eXtreme Shape Controller (XSC) algorithm enables the control of the full plasma boundary ~~system is no longer limited to the accurate control of only a few gaps~~all the circuits in shape controller are set to proportional current control~~current references provided by the XSC algorithm.~~algorithm is valid only around a given equilibrium~~~plasma must be driven into the reference conditions using shape controller• Current Limit Avoidance (CLA) uses the redundancy of the PF coil system ~automatically obtains almost the same plasma reference shape ~~with a different combination of currents in the PF coils~~in the presence of severe disturbances~~~tries to avoid the current saturations~~~by relaxing the plasma shape constraints

A. Neto, P. J. Lomas, F. Maviglia, D. Alves, I. S. Carvalho, G. De Tommasi, R. Felton, P. McCullen, V. Riccardo, F. G. Rimini, A. Stephen, R. Vitelli, K-D. Zastrow1 2 1 1 2 3 3 2 2 2 42 2

JET-EFDA, Culham Science Centre, OX14 3DB, Abingdon, UK1 Associação Euratom-IST, Instituto de Plasmas e Fusão Nuclear - Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, P1049-001 Lisboa, Portugal 2 EURATOM-CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3EA, United Kingdom 3 Associazione EURATOM/ENEA/CREATE, Università di Napoli Federico II, 80138 Napoli, Italy 4 Dipartimento di Informatica, Sistemi e Produzione, Università di Roma “Tor Vergata,” 00133 Rome, [email protected]