1 INPC07, Tokyo, June 8th Present Status and Future Prospects of the ITER Project N. Holtkamp June...

1INPC07, Tokyo, June 8th

Present Status and Future Present Status and Future Prospects of the ITER ProjectProspects of the ITER Project

N. HoltkampN. HoltkampJune 8, 2007June 8, 2007

INPC07, TokyoINPC07, Tokyo


ITER – the way to fusion powerITER – the way to fusion power

• ITER (“the way” in Latin) is the essential next step in the development of fusion.

• Its objective: to demonstrate

the scientific and technological

feasibility of fusion power.

• The world’s biggest fusion energy

research project, and one of the

most challenging and innovative

scientific projects in the world today.


ITER historyITER history

• 1988-1991 - (CDA) Conceptual Design Phase – Start of common activities among EU,RF, 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, US re-joins, China & South Korea are accepted as full partners.– Cadarache selected as ITER site (28.06.2005), India joined in Dec 2005– Agreement initialised on May 24, 2006


Mutual trust is our greatest assetMutual trust is our greatest asset

Ceremony ITER Agreement Signature, Elysee Palace, 21 November 2006


Construction SharingConstruction Sharing

Overall sharing:EU 5/11, other six parties 1/11 each. Overall contingency of 10% of total. Total amount: 3577 kIUA (5079 Euro-2007)

European Union

CN

IN

RF

KO

JP

US

Total procurement value : 3021

Staff: 477

R&D: 80

Total kIUA: 3577


Construction Cost SharingConstruction Cost Sharing

C

“Contributions in Kind”Major systems provided

directly by Parties

B

Residue of systems,jointly funded,purchased by

ITER Project Team

A

Systems suited only to Host Party industry- Buildings- Machine assembly- System installation- Piping, wiring, etc.- Assembly/installation labour

Overall costs shared according to agreed evaluation of A+B+C

Overall cost sharing:EU 5/11, Others 6 Parties 1/11 each, Overall contingency up to 10% of total.


ITER – Key factsITER – Key facts

The current ITER building

Cadarache Site

• Designed to produce 500 MW of fusion power (tenfold the energy input)

for an extended period of time

• Will bring together most key technologies needed for future fusion power plants

• 10 years construction,20 years operation 5 years deactivation

• Cost: 5 billion Euros for construction, and 5 billionfor operation and decommissioning


JET (1983)

Q<1 t=1s

Pfus: 16 MW R=3m

Ip< 7 MABT0< 4T

Volume: 100 m3

JET (1983)

Q<1 t=1s

Pfus: 16 MW R=3m

Ip< 7 MABT0< 4T

Volume: 100 m3

ITER (2016)Q=10 t=400sQ=5 t=3000s

Pfus: 500 MW R= 6.2mIp: 15 MA

BT0< 5TPlasma volume:

840 m3


The Core of ITERThe Core of ITER

Toroidal Field CoilNb3Sn, 18, wedged

Central SolenoidNb3Sn, 6 modules

Poloidal Field CoilNb-Ti, 6

Vacuum Vessel9 sectors

Port Plug heating/current drive, test blanketslimiters/RHdiagnostics

Cryostat24 m high x 28 m dia.

Blanket440 modules

Torus Cryopumps, 8

Major Plasma Radius 6.2 m

Plasma Volume: 840 m3

Plasma Current: 15 MA

Typical Density: 1020 m-3

Typical Temperature: 20 keV

Fusion Power: 500 MWMachine mass: 23350 t (cryostat + VV + magnets)- shielding, divertor and manifolds: 7945 t + 1060 port plugs- magnet systems: 10150 t; cryostat: 820 t

Divertor54 cassettes


The ITER SiteThe ITER Site

• Will cover an area of about 60 ha• Large buildings up to 170 m long• Large number of systems

Tokamak building

Tritium building

Cryoplant buildings

Magnet power convertors buildings

Hot cell

Cooling towers


Integrated Project Schedule Integrated Project Schedule Top DownTop Down

10 years

2 years 8 years

2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015

ITER IO ESTABLISHED

LICENSE TO CONSTRUCT

START TOKAMAK ASSEMBLY

FIRSTPLASMA

Contract

EARTHWORKS

TOKAMAK BUILDING

OTHER BUILDINGS

TOKAMAK ASSEMBLY

COMMISSIONING

COILS

VACUUMVESSEL

InstallCryostat

1st VV/TF/TSSector

Complete VV

Complete BLK/DIV

1st PFC Install CS

First sector Last sector

Last CSLast TFC

1st PFC

1st TFC

Procurement & Fabrication

2016

Construction License Process

Last PFC

Procurement & Fabrication


Procurement SharingProcurement Sharing

PACKAGE kIUA ALLOCATION REMARKS

1A 85.2 EU=100% Toroidal Field Magnet Windings

1B 82.3 JA=100%

1A for 10 TF (including 1 prototype) and 1B for 9 TF (including 2.5 kIUA for fabrication verification)

2A 51.4 EU=10%, JA=90% Toroidal Field Magnet Structures 2B 47.7 JA=100%

Fabrication of whole structures by JA and Pre-compression ring (0.6 kIUA) by EU. Final assembly of 10 TF coil cases by EU (10%)

Magnet Supports 2C 22.85 CN=100%

Poloidal Field Magnet 1 & 6

3A 13.6 EU=50%, RF=50% PF1 by RF and PF6 by EU

Poloidal Field Magnet 2 to 5

3B 33.6 EU=100%

Correction Coils 3C 2.6 CN=100%

Central Solenoid Magnet

4A+4B

39.6 US=100%

Feeders 5A 26.15 CN=100%

Feeders Sensors 5B 18.05 FUND=100%

Toroidal Field Magnet Conductors

6A 215 EU=20%, JA=25%, RF=20%, CN=7%, KO=20%, US=8%

1.1

Magnet

Central Solenoid Magnet Conductors

6B 90 JA=100%

See Note-1

Example of the Procurement Sharing Agreements

Copy from the “Common understanding of procurement sharing”


The Scope, the Schedule and The Scope, the Schedule and the Cost of ITERthe Cost of ITER

• The Schedule: begin construction in 2007 and have first plasma In 2016.

• The Construction Cost: 3.578 kIUA (~5.000 M€)

– Including 80 kIUA R&D– Including 477 kIUA Project Team

• Reserve: 358 kIUA on request by NDG • Operations Cost for 25 years: 188 kIUA/year• Deactivation for 5 years: 281 kIUA • Decommissioning: 530 kIUA (host responsibility)


Main Management Structure Main Management Structure of the ITER IOof the ITER IO

See detailed chart


New Proposal of Long Term Staffing New Proposal of Long Term Staffing during Constructionduring Construction

• 2250 professional years and 1860 support staff years consistent with 477 kIUA

• Smooth transition to operation

0

100

200

300

400

500

600

700

2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016

Professional

Support

Total Staff


Cadarache & EnvironsCadarache & Environs


Site preparationSite preparation

• site clearing

• access to the site

©AIF

Main entrance

Secondary Access


Site preparationSite preparation

• site clearing


Contractors’ AreaContractors’ Area


Design ReviewDesign Review

• The first goal for 2007 is to create a new Baseline Design 2007 which– Confirms or redefines the physics basis and requirements for the project – Is the basis for the procurement of the long lead items (Vacuum Vessel,

Magnets, Buildings), – provides input for the Preliminary Safety Report

• The second goal is to base the ITER design decisions also in detail on a broad basis by involving the worldwide fusion community (physics and engineering)

– Thus the Fusion community and the parties can take ownership of the project

• The third goal is to broaden the knowledge basis into the parties which is essential for a successful procurement of the ITER components in kind

– A significant part of technical coaching of industry and of the QA will rest with the Domestic Agencies (DAs)

• For components and systems which are procured at a later date or for issues with lower priority work will continue into the year 2008


Design Review is performed by 8 Working GroupsDesign Review is performed by 8 Working Groups~150 members (see ~150 members (see Web Site Web Site ))

WG-1 Design Reqs. & Physics Objectives. Chair: P.Thomas; IO D.Campbell

WG-2 Safety and LicensingChair: J-P Perves; IO J-P.Girard

WG-3 Site and BuildingsChair: C.Strawbridge; IO J.Sovka

WG-4 MagnetsChair: M.Huguet; IO N.Mitchell

WG-5 Vacuum VesselChair: Songtao Wu; IO K.Ioki

WG-6 Heating and Current DriveChair: J.Jacquinot; IO A.Tanga

WG-7 Tritium PlantChair: D.Murdoch; IO M.Glugla

WG-8 In-Vessel ComponentsChair: Igor Mazul; IO M.Pick/C.Lowry

The membership consists of the

leading experts of the fusion community

in each party

The groups have written manifestos

explaining the scope of their work (see

ITER technical web)

In order to solve issues work packages

have been agreed with the parties

based on the work plans established by

the design review working groups

(80PPY)


Inital On Going Issues19

225

186

out of DRone WGshared

ITER IssuesITER Issues (Link: (Link: ITER Issues Data BaseITER Issues Data Base ) )

~ 200 issues existed for several years but were for different reasons not solved or rejected

Another ~ 250 were added by the parties last autumn when the design review process started

Thus ~ 450 issue cards existed when the design review working groups were formed in December of 2006 and started their work

At the moment we have 411 ongoing issues

186 issues require consideration by more than one group


Roles and Responsibilities for ConstructionRoles and Responsibilities for Construction

ITER Organization Seven Parties

• Planning / Design • Integration / QA /

Safety / Licensing / Schedule

• Installation • Testing +

Commissioning • Operation

• Detailing / Designing• Procuring• Delivering• Supporting installation• Conformance


DG

DAs

TechnicalWork

Tasks & R&D

Proc. Arrangement

IO – DAs collaboration schemeIO – DAs collaboration scheme

Config. Mngmt.

ITER Engineering Departments

ProjectOffice

SafetySecurity

QA

PDDG

FieldTeams

Proc. Control


The First Procurements: MagnetThe First Procurements: Magnet

1.1 Magnets Pkg Issue Date

Toroidal Field Magnet Windings

1A & 1B

Jan-08

Toroidal Field Magnet Structures

2A & 2B

Jan-08

Magnet Supports 2C Jan-08

Poloidal Field Magnet 1 & 6 3A Jan-08

Poloidal Field Magnets 2, 3, 4, 5

3B Jan-08

Correction Coils 3C Jan-08

Central Solenoid Magnet4A &

4BJun-08

Feeders 5A Jun-08

Feeder Sensors 5B Jun-08

Toroidal Field Magnet Conductors

6AAug-

07

Central Solenoid Magnet Conductors

6B Oct-07

Poloidal Field Magnet Conductors

6C Oct-07


Magnet ConductorMagnet Conductor• cables tested

in 2006 showed substantial degradation• Ongoing field-

cycling stress tests showing very promising results

Tentative ConclusionsThe OST strand is significantly more sensitive to strain than EAS. The long twist pitches provide better strand support than short. This is critical for OST, not for EAS. With OST small changes in strand support can provoke major performance degradation –question on OST strand suitability for CICC

Questions for further investigation (1)The TFPRO1-EAS1 leg performs better than TFAS-EAS leg. Why?Possibilities are: Higher joint resistance in TFAS is distorting interpretation. Overload of TFAS (high BI combination) at start of test. Comparing BI plots implies degradation model, not justified for different conductors


• Three equatorial ports are available for TBM testing

• Up to six different types of TBMs, with independent ancillary systems, could be simultaneously tested:

• Further time and space sharing not technically viable.

TBM R&D and Testing TBM R&D and Testing Program: Exploitation of ITERProgram: Exploitation of ITER

Summary of minimum Members’ requests on TBM leadership

PartyCeramic Breeder TBM

Liquid LiPb

TBM

Liquid Li TBM

CN1 HCCB DFLL

EU1 HCCB HCLL

IN- LLCB

JA1 WCCB

KO HCSB HCM

RF (Li/V)

US(DCLL)

Total 4 3+(1) 1+(1)


The TBMs first wall is recessed of 50 mm and protected with a Be layer

Shield plug

Frame

TBMLocation

TBM

TBMs tests need a whole TBM system

TBMs Arrangement in ITER and InterfacesTBMs Arrangement in ITER and Interfaces

TBM ports


JT-60

Fusion Plasma Research

Tokamak DEMO ReactorITER

ITER&DEMO Physics Support Activities

Component Technology

Test Blanket Module

Blanket TechnologyHeavy Irradiation

IFMIFStructure Development

Structural Material Dev.

Fusion Engineering Research

JT-60 Superconducting Coils

The Present and the FutureThe Present and the FutureRoad Map to Fusion DEMO ReactorRoad Map to Fusion DEMO Reactor


ITER 　 Cadarache

Satellite TokamakSatellite Tokamak

International Fusion Energy Research Center

DEMO Design and R&DCo-ordination Center

DEMO Design and R&DCo-ordination Center

ITER Remote Experimentation Center

ITER Remote Experimentation Center

ITER

Data Acquisition and Analysis

Setting Experimental Parameters

IFMIF-EVEDAIFMIF-EVEDA

IFMIF

Fusion Computer Simulation Center

Fusion Computer Simulation Center

Check of experimental conditions, Machine Control, etc

International Fusion Energy International Fusion Energy Research CenterResearch Center



SummarySummary

• ITER is worldwide one of the largest, if not the largest scientific project.

• It is the first project based on “in kind” contributions to such an extent.

• While ITER is supported in many ways by CEA and Europe, it is also a “green field” site, which means the creation of a new international organization.

• With ITER and the Broader approach DEMO is well on its way to become the final step for implementation of fusion power as a reliable source of energy.

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