F. GnesottoFrascati, 19 gennaio 2007 Giornata di presentazione del Progetto ITER all’Industria italiana Ruolo dell’Associazione Euratom-ENEA Prof. F. Gnesotto,

F. Gnesotto Frascati, 19 gennaio 2007

Giornata di presentazione del Progetto ITER all’Industria

italiana

Ruolo dell’Associazione Euratom-ENEA

Prof. F. Gnesotto, Consorzio RFX


L’iniettore di fasci di neutri di ITER

Il sistema di alimentazioni elettriche di JT-60 SA


5 m

Negative ions D- are generated in the ion source (required 200 A/m2 D-)

Extraction of 40 A D-

D- ions accelerated with 1 MV

Neutralization to D0 in the gas neutralizer

HV Bushing

(-1 MV inside)

16.7 MW D0

delivered to the ITER plasma

Electrostatic RID

(deflection of the residual charged beams)

Neutral Beam Heating and Current Drive in ITER


Neutral beam injection: principles

Ion source

NeutraliserResidual ion Dump (RID)

AcceleratorPlasma


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=16.5MWI=40AV=1MV ( to heat the core plasma)t pulse=3600s

1MeV neutrals implies negative ions for efficient neutralisation (60%)


NBI injectors in ITER

tangential injection

On/off axis injection by tilting the beam axis vertically

Plan viewVertical cross section view

DNB

2+1 NBI


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.


The injector

15m 5m

9m


Power balance [MW] with 1MeV D Beam

POWER SUPPLY

BEAM SOURCE

BEAM LINE

TRANSMISSION LINE

POWER SUPPLY

0.05

24

INPUTPOWER

481

1720to PLASMA

5559

5

40

NEUTRALISER

CALORIMETER

RID

ION SOURCE

DUCT

0.6

POWER SUPPLY

BEAM BEAM LINE

OTHERCOMPONENTS

LINE

SUPPLY

0.05

25

ACCELERATOR

INPUTPOWER

481

1620to PLASMA

5559

5

40

0.25

SOURCE

17181718


An example: the Neutralizer

2500

3200

1875 O/ALL

720

H2 or D2

inletCooling water i/o

H- or D- Beam

• 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

Power deposition from ion beam interception:

• Beam on/off 5x104

• Breakdowns 4.5x105

Heating cycles during ITER lifetime:

Additional power deposition due to electrons (stripping losses in SINGAP):

• on leading edges 2.7 MW (max. 26-30 MW/m2)


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.

STEP UP TRANSFORMERS

POWER SUPPLY BUILDING

TRANSMISSION LINE

HV DECK

BUSHING

\\70m


Acceleration Grid Power Supplies

0 V

-1 MV

Ac/dc converter Dc/ac inverter

Step-up (isolation)Transformer

-800 kV

-600 kV

-400 kV

-200 kV

69 kV

59 A

7 A

6 A

3 A

3 A

40 A

Step-down Transformer

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 s


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

Test Facility


Test Facility for a generic site

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

Power supplyMaintenance

Experiment

Auxiliary systems

Cooling towers

Test Facility for a generic site


Test Facility Auxiliary Systems

Cryosystem

Forepumpingsystem

Top flange platform

60 MW cooling tower

Heat rejection system

Primary Heat

Transfer System

HV deck

TL2

TL1

HV deckplatform

Experiment ground

level

gas

100m

The auxiliary systems consist of

cryogenic plant

cooling plant

pumping and gas injection plant


Costi (M€)

Convertitori 27.0

Installazioni e collaudi 5.0

Sorgente del fascio 7.0

Neutralizzatore, RID, calorimetro 5.1

Vessel e condotto 8.0

Bobine di compensazione 7.9

Totale EU 60.0

Componenti assegnati a EU

Costi per 2 iniettori


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.

The Broader Approach Agreement


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)


The satellite Tokamak: JT-60SA

M.Matsukawa, Eng. Feature in the design of JT-60SA, IAEA 06

Outline of the JT-60SA Device


Parties contribution to the JT-60SA construction and operation

Approximated data in percentage

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€)

EU(%) JA(%)TF magnet 96 4PF magnet 4 96VV 0 100In-vessel 0 100PS+Contr. 100 0Cryostat 73 27Cryogenic 100 0Assembly 0 100ECRF4MW,140GHz 52 48Remote Handling 0 100Transportation cost 0 100Common cost 0 100

50 50Operation

Component


The quench protection system for JT-60SA

First RFX design activity:Identification of the technical solution

•vacuum Circuit Breaker (VCB) VCB with mechanical bypass in parallel like in the protection unit developed for ITER

•semiconductorsa 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

Quench Protection SystemJA conceptual design

R

MSVCB

S

CCH

DFuse

Pyro-FuseMCB

+-

Backup circuit

Dump resistance

Coil current


Sector Coil

AC filter

PWM Inverter

6 coils for toroidal direction

Thyristor Converter

DCL

～

～～

The fast power supply for the in vessel sector coil of JT-60SA


The IFMIF Facility


The accelerator

The RFQ will be built under responsibility of INFN


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€.

Documents

F. GnesottoFrascati, 19 gennaio 2007 Giornata di presentazione del Progetto ITER all’Industria italiana Ruolo dell’Associazione Euratom-ENEA Prof. F. Gnesotto,