A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 1

The ITER Neutral Beam injectors

Antonio Masiello

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 2

Ion source

NeutraliserResidual ion Dump (RID)

AcceleratorPlasma

Neutral Beam injection: principles

D beam

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 3

The configuration of the NB injectors in ITER

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 4

The Neutral Beam injector

Cryopump

Beam Source Vessel

Neutralizer

Beam Line Vessel

HNB source

Bottom Active coils

RID

Calorimeter

Bushing

Top Active coils

Passive Magnetic Shield

Fast shutter

Absolute valve

VVPSS box

Drift Duct

Beam Source Vessel rear door

Beam Line Vessel top lid

Cryopump

Beam Source Vessel

Neutralizer

Beam Line Vessel

HNB source

Bottom Active coils

RID

Calorimeter

Bushing

Top Active coils

Passive Magnetic Shield

Fast shutter

Absolute valve

VVPSS box

Drift Duct

Beam Source Vessel rear door

Beam Line Vessel top lid

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 5

The NB injector

POWER SUPPLY

BEAM SOURCE

BEAM LINE

POWERSUPPLY

0.05

24

INPUTPOWER

481

1720to PLASMA

5559

5

40

NEUTRALISER

CALORIMETER

RID

ION SOURCEDUCT

0.6

POWER SUPPLY

BEAM BEAM LINE

OTHERCOMPONENTS

TRANSMISSION LINE

0.05

25

ACCELERATOR

INPUTPOWER

481

1620to PLASMA

5559

5

40

0.25

SOURCE

17181718

Power delivered to the plasma per injector 16.5 MW

Beam energy 1 MeV

Ion species D-

Accelerated ion current at the grounded grid 40 A

Average accelerated ion current density at the grounded grid 200 A/m2

Current density uniformity over the extraction area 10 %

Pulse length ≤ 3,600 s

NB Power balance and main specifications

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 6

The ion source

Coaxial RF conductors

Cooling manifolds

Capacitors

Cs ovens

Drivers

Source case

Rear view of the RF ion sourceHalf size ion source test facilityCourtesy of IPP-Garching

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 7

The MAMuG accelerator

δAEG=0.6 mm AEG

BE

G

δBEG=0.15 mm

1280 apertures 4 segments x 4 groups, 5x16 apertures in a group

1MV accelerator 5 stages of 200kV

1 segment

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 8

The Beam Line Components

NeutraliserRID Calorimeter

Component Neutraliser Rid Calorimeter

Max heat load [MW] 4.56 20 22

Max PD [MW/m2] 2.1 6 22

Max water flow [Kg/s] 30 90 198

The beam line components

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 9

The NB high vacuum pumping

Neutraliser

1 module with 4 sections in parallel

Cryopanel: 4.6K supercritical He

Shielding: 80K gaseous He

1 section

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 10

The Power supplies

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 11

The Power supplies

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 12

Neutral Beam Test Facilityat Padua - Italy

The main risk mitigation measure for resolving NB issues

The NBTF lay-out reproduces the one of the ITER NB-1

A full size source

to start in 2012

A full neutral beam line to start in 2014

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 13

Global operating states

Construction and Long Term Maintenance (LTM)Short Term Maintenance (STM)Test and Conditioning Operation (TCS)

Cryopump regeneration at 400 K Cryopump cool-down Cryopump warm-up to ambient temperature HV conditioning over extraction and acceleration grids ion source plasma without extraction ion beam accelerated ion beam neutralized residual ion dump active

Short Term Stand-by (STS) Cryopump regeneration at 100 K

Pulse Operation State (POS) Beam on calorimeter Beam on target without plasma Beam on target with plasma: beam normal operation of in ITER pulse.

Beam is interlocked (e.g. tokamak plasma density)

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 14

Control system main parameters

The NB Injector Control System will control the following main parameters:

Power to the RF driver Plasma grid current Bias Voltage Extraction grid voltage Acceleration grids voltages Residual Ion dump biasing Caesium oven temperature Gas flows Fast shutter control (and absolute valve) Beam on/off-axis injection Magnetic compensation coil current …

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 15

Control system preliminary architecture (NBTF)

CSS Central Safety System CIS Central Interlock SystemPSS Plant Safety system PIS Plant Interlock System

Courtesy of the RFX Association

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 16

Main acquisition requirements

The data acquisition system of each NB Injector will include the instrumentation needed to condition, record, display and analyze the measured signal coming from the beam line

• Standard analog inputs to CODAC some thousands• Standard digital inputs to CODAC about 100• Standard digital outputs from CODAC about 100• Timing outputs from CODAC few

Temperature measurements Status signals Gas pressure meas. Residual pressure meas. B field (static) meas. Position transducers Water and gas flow meas. ……

Most of the signals sampling speed is 10-100Hz

For higher speeds up to MHz, a baseline speed of KHz is foreseen and an event driven acquisition with a window of few ms to acquire the signal up to some MHz

Fastest interlock 100s

A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” - 27-28 October, Barcelona 17

References

ITER neutral beam heating and current drive system 2001 Design Description Document N53 DDD

V. A., Final reports, EFDA contract: TW6-THHN-NBD1

A. Luchetta et al., Final report - Preliminary specification of the architecture of the control, interlock and safety systems for the NB test facility - EFDA contract: TW6-THHN-NBTF1

Plant control design handbook https://user.iter.org/?uid=27LH2V&version=v3.0

Systems Requirement Document (SRD) NBH and CD PBS 53

L. Svensson, private communication