ITER Technical Overview

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ITER: Technical Overview

W.Spears

ITER International Team

Ljubljana, 1st June, 2006


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1st June 2006 ITER Technical Overview - Ljubljana 2

ITER History

1988-1991 - (CDA) Conceptual Design Phase Start of common activities among EU,USSR, USA and JA.

Selection of machine parameters and objectives.

1992-1998 - (EDA) Engineering Design Phase

Developed design capable of ignition - large and expensive. The Parties (EU, JA, RF, US) endorsed design but could not afford to build it.

1999 2001 (EDA continues)

US withdraws from project.

Remaining Parties searched for less ambitious goal. New design: moderate plasma power amplification at about half the cost.

2001 - now (CTA and ITA)

End of EDA and start of negotiations on construction and operation.

4 site offers. 2003: US re-joins, China & South Korea are accepted as full partners.

Cadarache selected as ITER site in June 2005.

India joins in December 2005


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Technical Objectives

Q (ratio of fusion power to auxiliary heating power) 10(>5 in steady state). Possibility of controlled ignition.

Integrate the technologies essential for a fusion reactor (e.g.superconducting magnets, remote maintenance);

Test components for a future reactor (e.g. divertor and torusvacuum pumps, tritium breeding blanket modules).

Rely as far as possible on existing physics and tech. R&D.

Flexible operation range, with access to advanced modes.

Power flat top 300 s up to steady state.

Operation limited to ~30,000 pulses.

Average neutron flux > 0.5 MW/m2, fluence > 0.3 MWa/m2

Possible later installation of tritium breeding blanket.

Sufficiently reliable operation for nuclear testing.

Operate for ~ 20 years, using externally supplied tritium.


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ITER Plant



Plant Systems



Tokamak Building Complex

Hot Cell

TokamakAssembly Area


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JET

R=3m

Ip=4MAITERR=6.2m

Ip=15MA


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Shield

Magnet

System

Vacuum Vessel

Person

Tokamak

R=6.2 m

Ip=15 MA

Pfus=500 MW

Divertor

30 m

24 m


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Superconducting. Nb3Sn toroidal field (TF)coils produce confining/stabilizing toroidal field;

NbTi poloidal field (PF) coils position andshape plasma;

Modular Nb3Sn central solenoid (CS) coilinduces current in the plasma.

Correction coils correct error fields due tomanufacturing/assembly imperfections, andstabilize plasma against resistive wall modes.

TF coil case provides main structure of themagnet system and the machine core. PFcoils and vacuum vessel are linked to it. Allinteraction forces resisted internally.

TF coil inboard legs wedged together alongtheir side walls and linked at top and bottom

by two strong coaxial rings which providetoroidal compression

On the outboard leg, out-of-plane supportprovided by intercoil structures integrated withTF coil cases.

.

Magnet System

Magnet system weighs ~ 8,700 t.


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CS Model Coil TF Model coil

Magnet EDA R&D


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Vacuum

Vessel

Blanket

Divertor


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Plasma Vacuum Vessel

Primary function

high quality vacuum for the plasma

first confinement barrier to radioactive materials

9 x 4 0vessel sectors.

Many ports for access:

-Diagnostics

-Maintenance

-Heating systems

-Fuelling/Pumping

-Inspection-Test Blankets

Double wall

Water cooled


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Blanket

440 blanket modules withdetachable faceted first wall (FW)

with Be armour on a water-cooled

copper substrate, attached to a

SS shielding block.

Blanket cooling channels are

mounted on the vessel.

Design strongly affected by needto resist electromagnetic forces.

Initial blanket acts solely as a

neutron shield, and tritium

breeding experiments are carriedout on test blanket modules

inserted and withdrawn at radial

equatorial ports.

Inlet/outlet

manifolds

First wall

panel

Hole to fit

flexible support

Flexiblesupports

Vessel

Shieldblock

Shear key

Gripping

hole

Electrical strap


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Divertor

54 cassettes.

Target and divertor floor form a V which traps

neutral particles, protecting the target plates,

without adversely affecting helium removal.

Large openings between the inner and outer

divertor balance heat loads in the inboard and

outboard channels.

Design uses C at the vertical target strike

points. W is the backup. C is best able to

withstand large power density pulses (ELMs,

disruptions), but produces tritiated dust and T

co-deposited with C which has to be

periodically removed. The choice can be made

at the time of procurement.

Vertical target (W part)

Dome (W)

Vertical target (C part)


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Heating/Current Drive

High energy (1 MeV D-) ion beams +

radio frequency heating tuned to key

plasma frequencies (ion, electroncyclotron, lower hybrid).

RF systems modular and

interchangeable in equatorial ports.

EC used in upper ports.

2 main beam-lines, with room for

third.

Initial installation 73 MW with room

for expansion to 130 MW.

Steerable mirror

Front shield

Waveguides Windows

Electron Cyclotron System

Equatorial Port Plug

E l f EDA R&D


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Examples of EDA R&D

Payload ~ 4 t, Arm length ~ 6m

Vehicle Manipulator System For Blanket Maintenance


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A bl


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Assembly

Lower cryostat, tokamak gravitysupports, lower PF and correction

coils, TF pre-tensioning rings, etc.,

placed in the pit.

40 sectors of vessel + 2 TF coils,thermal shields, etc., assembled

together on-site and moved to pit.

Sectors welded in opposition to

minimise distortions. TF coil pre-tensioning rings installed. Machine

datum established. Clean

conditions in-vessel.

In-vessel components installed andaligned. PF/correction coils and

cryostat above equator installed.

External installations proceed in

parallel.

Pl Ph i I


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MHD Stability

Heat Confinement

Steady State Operation

Control of Plasma Purity

Exploration of the new physics with adominant -particles plasma self heating

Plasma Physics Issues

E i i /T h l Ch ll


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Engineering/Technology Challenges

Change of extent of fusion research.

Many new problems to solve.

Millions of parts with very complex

interfaces and ensuing knock-on effects.

Unprecedented size of the

super-conducting magnet andstructures.

Extremely high heat fluxes in first

wall components, & materials

under neutron irradiation

Remote Maintenance required.


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Organisation Challenges (1)

Forging one coherent project team across multiple cultures(and time zones) with industrial support.



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Magnet System

Cryogenie

& Vessel

Internals

Others

Power Supplies

Distribution &

& Diagnostics

CODAC

Cooling Water

Systems

Buildings

Assembly & R/H Cryostat & TS

EU

China

USA

India

RF

JapanS Korea


In-Kind?

Involve all the Parties in key fusion technology areas.

Share the cost of the device by value and not by currency.

Automatically ensure fair return Sharing: 5/11 EU (1/11 procured in Japan), 1/11 Others. (of which

10% centrally funded and 90% in-kind)

Procurement Sharing


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Procurement Sharing

Negotiation Status


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Negotiation Status

ITER Parties are now in the process of finalising the JointImplementation Agreement and its main instruments. Main Agreement Text

Staffing regulations Procurement and cost sharing

Intellectual Property Rights

Principles of Operation Programme

Resource Management Principles on management

November 2005: High level P Meeting, DG selected

December 2005: NSSG13/N Meeting , Finalisation of Drafts

May 2006: Ministerial Meeting to initial Agreement

November 2006: Agreement Formal Signature

Early 2007: Agreement enters into force

Continuing Design Process


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Continuing Design Process

In mid-2001 design finalised to extent allowing reasonablecost estimate to be made - ~ 5B + 5B during operation.

Continued design improvement since then, focussing onlong lead items (buildings/tunnels, magnets, vessel) andtheir interfaces.

Many improvements made to increase realism of costing

and to simplify design, operation or manufacture, reducerisk, or ease licensing.

Project infrastructure improvements to tighten up on

design change control and quality management -document and model management systems.

Strong emphasis now on licensing and preparation ofdocumentation for it. Design to be reviewed by new team

and then regularly as construction proceeds.

Schedule


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Schedule

2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015

ITER IOLICENSE TO

CONSTRUCT

TOKAMAK ASSEMBLY

STARTS

FIRST

PLASMA

BidContract

EXCAVATETOKAMAK BUILDING

OTHER BUILDINGS

TOKAMAK ASSEMBLY

COMMISSIONING

MAGNET

VESSEL

Bid Vendors Design

Bid

Install

cryostat

First sector Complete VVComplete

blanket/divertor

PFC Install CS

First sector Last sector

Last CSLast TFCCSPFC TFCfabrication start

Contract

Contract

2016

Construction License Process

Conclusions


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Conclusions

ITER is one of the most technologically, organisationally and politicallychallenging projects being undertaken today.

Nevertheless, a convincing design has been and continues to be developedable to meet its objectives, and the international infrastructure and the

organisation necessary to build it on the expected timescale is in theprocess of being set up.

ITER will be the proving ground for the key technologies necessary to makemagnetic fusion into a viable energy source.

The design phase has demonstrated the desirability of jointly implementingITER in a broad-based international collaborative frame with the stronginvolvement of Industry.

Procurement is split among the ITER Parties, but Europe provides 36% of

the hardware. This allows considerable opportunities for Europeanmanufacturers and service providers.

In its host role, Europe is well-placed to gain essential know-how from itsinvolvement in most systems, via installation and plant licensing.

ITER Technical Overview

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