Transcript Document

Negative Ion based Heating and
Diagnostic Neutral Beams for
ITER
B. Schunke
D. Bora, J.-J. Cordier, R. Hemsworth, A. Tanga
V. Antoni & RFX Team
T. Bonicelli & EU NB group
A. Chakraborty & IN NB group
T. Inoue, K. Watanabe & JA NB group
1
17th IAEA TM on Research Using Small Fusion Devices , Lisbon
B. Schunke
ITER
24 m
R=6.2 m
Ip=15 MA
Pfus=500 MW
30 m
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Neutral Beams for ITER
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• Introduction
• Negative Ion Beams for ITER
– The Heating Neutral Beams
– The Diagnostic Neutral Beam
• Neutral Beam R&D
• Summary and Outlook
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Introduction
Mission for H&CD systems for ITER
H&CD systems in ITER
• must provide the tools necessary to achieve the
production of thermonuclear power and Q=10
and to demonstrate the feasibility of fusion
power;
• demonstrate sufficient current drive (CD)
capability to aim at steady state operation;
• provide additional “services” such as mode
control, machine conditioning and assist in
plasma start up and diagnosis;
• have the flexibility to insure effective and stable
burn control.
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Introduction
Operation scenarios
• Plasma operation has been designed with variable
combinations of heating and current drive systems:
2 (3) NB H&CD injectors 33 – 50 MW, 20~40MW ECH,
20~40MW ICH, 0~40MW LH;
3 MW ECH for start up, 3.5 MW DNB.
• ITER Baseline 2004: Start-up configuration requires
33 MW NB (2), 20MW ICH, 20MW ECH, 0MW LH;
3 MW ECH for start up, 3.5 MW DNB on Day1.
• The machine configuration is consistent with the
possibility of implementation of various operating
scenarios. Infrastructure for Heating systems has to be
compatible.
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Introduction
DESIGN SCENARIOS FOR ITER OPERATION
Start up
Power
[MW]
NB
IC
EC
LH
Total
Installed
33
20
20
0
73
Scenario 1
Scenario 2
Scenario 3
Scenario 4
ELMy Hmode
ELMy Hmode
Steady State
High ne
Low ne
Hybrid
scenario
No. of Power No. of Power No. of Power No. of Power No. of
Equat. [MW] Equat. [MW] Equat. [MW] Equat. [MW] Equat.
ports
ports
ports
ports
ports
2
33
2
50
3
50
3
50
3
1
40
2
20
1
40
2
20
1
1
40
1
40
1
40
1
20
0
0
20
1
20
1
0
0
40
2
4
133
6
130
6
130
6
130
6
ITER baseline scenarios foresee large (40%) contribution from NB heating,
3rd injector needed for scenarios 2-4
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Negative Ion Beams for ITER
Summary of the design parameters for heating and
current drive (H&CD) & Diagnostic NBI system for ITER.
Power delivered to the plasma
per injector
HNB (2 + 1)
16.7 MW
DNB
3.6MW (excl.
duct losses)
Beam energy
1MeV (D-) / 870keV
100 keV (H-)
(H-)
Accelerated ion current
40 A (D-) / 46 A (H-)
60 A (H-)
Average accelerated ion current
density
200 A/m2 (D-) / 300
A/m2 (H-) ****
300 A/m2
Current density uniformity over
the extraction area
 10 %
 10 %
Pulse length
≤ 3600 s
5Hz mod. 1/6
ITER pulse
Beamlet divergence
< 7 mrad
< 7 mrad
**** achieved 280 A/m2 of H for < 5s
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Negative Ion Beams for ITER (HNB)
The HNB injector
The Injector can be separated in
beam components (Ion Source, Accelerator, Neutralizer, Residual Ion
Dump and Calorimeter)
other components (cryo-pump, vessels, fast shutter, duct, magnetic
shielding, and residual magnetic field compensating coils), bushing
Weight >250 tons
9m
Connected
to tokamak
via NB duct
15m
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Negative Ion Beams for ITER (DNB)
DNB needed for Charge Exchange Recombination
Spectroscopy (CXRS), only possibility to measure He density
profiles in a tokamak (He ash); also self consistent code CHEAP
CXRS cross sections of atomic transitions => beam energy
Good S/N => High current density & beam divergence, beam
modulation
Upper
correction
coils
Same RF ion
source, but
simplified
accelerator
But higher
current
density:
material
fatigue
limitations
Bushing
PMS
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Beam
Beam
vessel
Passive Magn.
Shield
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Negative Ion Beams for ITER
West
The NB injectors are
installed in the
equatorial level of
the tokamak
building: NB cell
NB directly
connected to
torus vacuum =>
high dose rate,
high activation
Remote handling for
interventions and
maintenance
Temporary wall to
allow installation
of the 3rd injector
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HNB#3
HNB#2
North
HNB#1
DNB
East
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Negative Ion Beams for ITER
NB Power Supplies
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Negative Ion Beams for ITER
All Heating and Current Drive systems are procured in kind
HNB and DNB
ICH & CD
ECH & CD, Start up
LHCD
( EU & JA, IN )
( EU, US, IN )
( EU, JA, RF, IN )
(no procurement package)
ITER IO provides integration
Department for CODAC & IT, Heating and CD, Diagnostics (CHD) –
Director D. Bora (presentation Wednesday 9:00)
H & CD Division:
ITER Man Power
Head A. Tanga
S.H. : Senior Technical Officers (3.5 of 5)
Phy/Eng : Technical Officers (9)
Technical Assistants : (28)
R. Hemsworth (NB), B. Schunke (NB), B. Beaumont (ICH &LH),
N. Kobayashi (ECH)
ITER relies on collaboration with partners, who have chosen to set
up ITER in this form
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Neutral Beam R&D
ITER Research & Development Brief
• H&CD systems must be built and installed in ITER
minimizing cost and risk in order to be on schedule and
operate efficiently.
• H&CD systems are critical & essential for fusion
research; hence critical technologies need to be
developed for ITER and for DEMO.
• Pursue collaboration of the whole fusion community in
the development and research in various areas related to
H&CD systems.
• It is foreseen that following the initial operations, systems
will be upgraded during the operational phase of ITER.
=> applicable to NB systems
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Neutral Beam R&D
Present plan for NB R&D (Host EU, but JA
and IN part.)
• Establish Neutral Beam Test facility (NBTF) at Consorzio
RFX, Padua, Italy (full 1MeV capability)
• The present plan is to start very early (tendering Jan
2008), the procurement of a full body of one injector and
install in Padua for a total time of 10 years.
• Additionally there will be a second test line devoted to the
development of the NB source, common between HNB
and DNB, and the testing of DNB (possible in India).
• Non reusable items and special R&D will be supported by
ITER R&D cash fund with a total sum of 8.8 kIUA.
• Building and services 31MEuros EU+Host
• Manpower for detail design (EU-JA-IN 2007-2011) and
20-40 professionals for operations (EU+PTs TBN)
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Neutral Beam R&D
ITER HNB – Neutral beam test facilty
Generic NBTF site layout
A full power 1MeV, 40A,
D-, 3600 s test bed will
be built at RFX, Padua,
Italy
Experiment
Maintenance
Power supply
Cooling towers
Auxiliary systems
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Neutral Beam R&D
Milestones
1. Start tendering Jan 2008
2. Shipping of High Voltage JA PS to test facility Jan 2012
3. Common testing of the HNB & DNB Ion source with
complete optimization for DNB Aug 2010 to 2013
4. Test of DNB start 2012 end 2015
5. Start HV tests Feb 2013 end 2017
6. Delivery schedule: Injector-1 will be assembled directly in
Cadarache by 2016 with inputs from R & D.
Injector-2 in End 2017 from Padua.
7. DNB components are brought to Cadarache Jan 2016.
Target: First ITER plasma end of 2016
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Neutral Beam R&D
Additional (and possible future) support (non exclusive):
Accelerator testing in 1MeV testbeds in CEA Cadarache, JAEA JA
Ion source development MPI, Garching, Germany ****
Calorimeter design IN collaborated with NB Juelich, Germany
Cryo-pump development, FZK Karlsruhe, Germany
Neutralizer Modeling, CNRS, France
Negative Ion Source Modeling & Ion Source Diagnostics, Sofia
University, Bulgaria
Worldwide collaboration
Active support from CCNB (Coordinating Committee on Neutral Beams)
Create forum for exchange / workshop / meeting to accompany NB
R&D
**** Schroedinger Preis der Helmholtzgesellschaft 2006
Adopted as ITER reference ion source, DCR in 2007
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Neutral Beam R&D
Additional (and possible future) support (non exclusive):
• Basic physics studies of beam plasma interaction
• Alternative ion source development (alternative to
caesium ?)
• Alternative (optical) neutralizer design
• Material testing
• Development of neutral beam code
• Beam plasma interaction physics
ITER Tasks, can be given to individual labs or DA, also
ITER R&D fund for specific tasks
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Summary and Outlook (1)
Summary
• Work in 2007 has concentrated on finalizing Baseline
2007
• Procurement arrangement for the NBTF: power supply
and sources
• NB cell design including Integration tasks:
– Finalize NB Cell lay-out
– Installation sequence studies
– Cooling requirements
Ongoing
• Complete documentation and interface documents, e.g.
Plant breakdown structure (PBS); System requirements
document (SRD)
• Implementation of the Design Change Requests from
design review
• R & D in specific areas of all H&CD including NBs to
meet Day 1 requirements
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Summary and Outlook (2)
Outlook
• Neutral Beam design freeze January 2008 so that the
detailed design phase can start.
• Majority of procurement packages to be issued in 2008
• NBTF full power testbed for NB issues in Padua, Italy:
collaboration of EU, JA, IN
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