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Giornata di presentazione
del Progetto ITER all’Industria italiana
Ruolo dell’Associazione
Euratom-ENEA
Prof. F. Gnesotto, Consorzio RFX
F. Gnesotto
Frascati, 19 gennaio 2007
L’iniettore di fasci di neutri di ITER
Il sistema di alimentazioni elettriche di JT-60 SA
F. Gnesotto
Frascati, 19 gennaio 2007
Neutral Beam Heating
and Current Drive in ITER
HV Bushing
(-1 MV inside)
16.7 MW D0
delivered to the ITER plasma
Electrostatic RID
(deflection of the residual charged beams)
Neutralization to D0 in the gas neutralizer
D- ions accelerated with 1 MV
Extraction of 40 A
5m
D-
Negative ions D- are generated in the ion source (required 200 A/m2 D-)
F. Gnesotto
Frascati, 19 gennaio 2007
Neutral beam injection: principles
Accelerator
Ion
Neutraliser
source
F. Gnesotto
Residual ion
Dump (RID)
Plasma
Frascati, 19 gennaio 2007
ITER NBI requirements
Neutral beam injection is required since the beginning of ITER operation
The NBI system consists of 2 (+1) beams for Auxiliary Heating and
Current Drive
Beam parameters:
P=16.5MW
I=40A
V=1MV ( to heat the core plasma)
t pulse=3600s
1MeV neutrals implies negative ions for efficient neutralisation (60%)
F. Gnesotto
Frascati, 19 gennaio 2007
NBI injectors in ITER
2+1 NBI
tangential injection
DNB
Plan view
Vertical cross section view
On/off axis injection by tilting the beam axis vertically
F. Gnesotto
Frascati, 19 gennaio 2007
The NBI sub-systems
The NBI system can be separated in 4 subsystems:
a)
The Injector
b) The Power Supply and Voltage Distribution System
c)
The Control and Data Acquisition System
d) The Auxiliary Systems.
F. Gnesotto
Frascati, 19 gennaio 2007
The injector
9m
15m
F. Gnesotto
5m
Frascati, 19 gennaio 2007
Power balance [MW] with 1MeV D Beam
POWER
SUPPLY
5559
BEAM
SOURCE
INPUT
POWER
1
5
5
BEAM LINE
40
48
0.05
24
25
1718
0.2
DUCT
ION SOURCE
POWER
SUPPLY
to PLASMA
CALORIMETER 0.6
TRANSMISSION
LINE
OTHER
COMPONENTS
1720
1620
NEUTRALISER
ACCELERATOR
RID
F. Gnesotto
Frascati, 19 gennaio 2007
An example: the Neutralizer
Power deposition from ion beam interception:
• on channel walls 4.2 MW (max. 0.5 MW/m2)
• on leading edges 0.4 MW (max. 2.2 MW/m2)
• Total power
4.6 MW
720
3200
H- or D- Beam
2500
Heating cycles during ITER lifetime:
H2 or D2
inlet
Cooling water
i/o
F. Gnesotto
• Beam on/off
• Breakdowns
5x104
4.5x105
1875 O/ALL
Additional power deposition due to electrons
(stripping losses in SINGAP):
• on leading edges 2.7 MW (max. 26-30 MW/m2)
Frascati, 19 gennaio 2007
The Power Supply
and Voltage Distribution System
The Power Supply (PS) and Voltage Distribution System provides the High Voltage
(HV) to the accelerator grids (AGPS) and supplies the ion source (ISPS) and the
auxiliary components.
The power is transmitted to the ion source and the acceleration grids via a HV
transmission line, SF6 insulated for -1MV dc to ground.
TRANSMISSION LINE
HV DECK
BUSHING
\\
70m
POWER SUPPLY
BUILDING
F. Gnesotto
STEP UP
TRANSFORMERS
Frascati, 19 gennaio 2007
Acceleration Grid Power Supplies
MAMuG Configuration
Parameter
Value
Main supply
-1000 kV / 59 A
Grid 1
-800 kV / 7 A
Grid 2
-600 kV / 6 A
Grid 3
-400 kV / 3 A
Grid 4
-200 kV / 3 A
Current at ground
level
40 A
Max. voltage ripple
5%
Response time of
the load protection
system
< 200 ms
F. Gnesotto
Frascati, 19 gennaio 2007
Test Facility
 As
most of the issues are strongly coupled, they can be tackled and solved
only by testing a full scale NBI at full performance in D and H.
 A Test Facility to install and operate a NBI before operation in ITER is
therefore mandatory in order to provide a reliable system.
 The test facility will be built in Padova
F. Gnesotto
Frascati, 19 gennaio 2007
Test Facility for a generic site
Test Facility for a generic site
Experiment
Maintenance
Power supply
Cooling towers
Auxiliary systems
At present work is in progress to adapt the generic site to Padova site, which has been
proposed by EU as the Test Facility site
F. Gnesotto
Frascati, 19 gennaio 2007
Test Facility Auxiliary Systems
cryogenic plant
cooling plant
The auxiliary systems consist of
pumping and gas injection plant
TL1
HV
deck
HV deck
platform
TL2
Top flange
platform
Experiment
ground
level
gas
Heat
rejection
system
Primary
Heat
Transfer
System
60 MW
cooling
tower
Cryosystem
F. Gnesotto
Forepumping
system
100m
Frascati, 19 gennaio 2007
Costi (M€)
Componenti assegnati a EU
Costi per 2 iniettori
Convertitori
Installazioni e collaudi
Sorgente del fascio
Neutralizzatore, RID, calorimetro
Vessel e condotto
Bobine di compensazione
Totale EU
F. Gnesotto
27.0
5.0
7.0
5.1
8.0
7.9
60.0
Frascati, 19 gennaio 2007
The Broader Approach Agreement
Projects identified:
• Engineering Validation and Engineering Design Activities for International
Fusion Materials Irradiation Facility (IFMIF-EVEDA and/or facility) to
qualify the structural materials needed to license DEMO.
• International Fusion Energy Research Center (IFERC) including a computer
simulation center for fusion science, a center for remote experimentation and
a center for international design activities for demonstration reactors
• A new plasma experimental device (Satellite Tokamak), named JT-60SA, in
Naka, Japan.
F. Gnesotto
Frascati, 19 gennaio 2007
The Broader Approach Agreement
Allocation of contributions of the Parties (in percentage)
Project
EU
JA
Sum
IFMIF-EVEDA
14,4
7,6
22,0
IFERC
12,0
18,7
30,7
Satellite Tokamak
(JT-60SA)
23,6
23,6
47,3
Total
50
50
100
Europe contribution 338 M€ (value 5 May 2005)
Japanese contribution 46 BY (value 5 May 2005)
F. Gnesotto
Frascati, 19 gennaio 2007
The satellite Tokamak: JT-60SA
Outline of the JT-60SA Device
M.Matsukawa, Eng. Feature in the design of JT-60SA, IAEA 06
F. Gnesotto
Frascati, 19 gennaio 2007
Parties contribution to the JT-60SA
construction and operation
EU(%)
Component
Operation
TF magnet
PF magnet
VV
In-vessel
PS+Contr.
Cryostat
Cryogenic
Assembly
ECRF4MW,140GHz
Remote Handling
Transportation cost
Common cost
JA(%)
96
4
0
0
100
73
100
0
52
0
0
0
50
4
96
100
100
Approximated data
0 in percentage
27
0
100
48
100
100
100
50
The POWER SUPPLIES will be provided by EUROPE
Consorzio RFX will be responsible of:
• The quench protection system for the superconducting coils (13 M€)
• The fast power supply system for the in vessel sector coils (0.8 M€)
F. Gnesotto
Frascati, 19 gennaio 2007
The quench protection system for JT-60SA
Quench Protection System
JA conceptual design
First RFX design activity:
Identification of the technical
solution
S
MS
C
+
VCB
R
D
Dump
resistance
Coil current
F. Gnesotto
CH
Fuse
Pyro-Fuse
MCB
Backup circuit
•vacuum Circuit Breaker (VCB)
VCB with mechanical bypass in parallel
like in the protection unit developed for
ITER
•semiconductors
a solution based on semiconductors (like
the dc current breakers in RFX toroidal
circuit) should be possible for this voltage
and current rating and could be
preferable
Frascati, 19 gennaio 2007
The fast power supply
for the in vessel sector coil of JT-60SA
Sector Coil
Thyristor
Converter
DCL
AC filter
6 coils for
toroidal direction
～
～
～
PWM Inverter
F. Gnesotto
Frascati, 19 gennaio 2007
The IFMIF Facility
F. Gnesotto
Frascati, 19 gennaio 2007
The accelerator
The RFQ will be built under responsibility of
INFN
F. Gnesotto
Frascati, 19 gennaio 2007
The RFQ
RFQ (Radiofrequency Quadrupole) Linac
The RFQ accelerates the beam of 125mA from 95 keV to 5 MeV
A longitudinal length of 12.5m is needed
The RF operating frequency is 175 MHz
RFQ cold model
( CEA Sacley, IPHI-350MHz )
RFQ cold model
( JAERI, 175MHz-4m module )
The budget for RFQ is 17.3 M€.
F. Gnesotto
Frascati, 19 gennaio 2007