1. The ITER Neutral Beam injectors
Antonio Masiello
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

2. Neutral Beam injection: principles
Residual ion
Dump (RID)
Accelerator
Ion
source
Neutraliser
Plasma
D beam
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

3. The configuration of the NB injectors in ITER
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

4. The Neutral Beam injector
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

5. NB Power balance and main specifications
BEAM
BEAM
BEAM LINE
BEAM LINE 55 55 59 59
SUPPLY
SUPPLY
SOURCE
SOURCE 40 40 16 17 20 20
INPUT
INPUT
0.05
0.05
The NB injector
POWER
POWER 17 17 18 18 to to
PLASMA
PLASMA 1 1 2 2 4 5
0.2 4 4 8 8 5 5 5
CALORIMETER
0.6
TRANSMISSION
LINE
ION SOURCE
NEUTRALISER
DUCT
OTHER
COMPONENTS
POWER
SUPPLY
RID
ACCELERATOR
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
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

6. The ion source Half size ion source test facility
Courtesy of IPP-Garching
Rear view of the RF ion source
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

7. The MAMuG accelerator 1MV accelerator 5 stages of 200kV 1 segment
1280 apertures
4 segments x 4 groups, 5x16 apertures in a group
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

8. The Beam Line Components
Neutraliser
Rid
Calorimeter
Max heat load [MW]
4.56 20 22
Max PD [MW/m2]
2.1 6
Max water flow [Kg/s] 30 90
198
The Beam Line Components
Neutraliser
Calorimeter
RID
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

9. The NB high vacuum pumping
1 section
Cryopanel: 4.6K supercritical He
Shielding: 80K gaseous He
1 module with 4 sections in parallel
Neutraliser
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona

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

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

12. Neutral Beam Test Facility at 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” 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” 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” October, Barcelona

15. Control system preliminary architecture (NBTF)
CSS Central Safety System CIS Central Interlock System
PSS Plant Safety system PIS Plant Interlock System
Courtesy of the RFX Association
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” 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 Hz
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 100ms
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” 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
Systems Requirement Document (SRD) NBH and CD PBS 53
L. Svensson, private communication
A.Masiello – Colloquium on the ITER-CODAC “Plant Control Design Handbook” October, Barcelona