December 14, 2001ITC12

Status of ITER Project

Presented by T.Tsunematsu(EDA JA Home Team Leader)

Japan Atomic Energy Research Institute

Reference Schedule of ITER Project

88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05

CDAITERConceptualDesignActivities

400ppy

EDAITER EngineeringDesign Activities1,420ppyTechnology R&D,Physics R&D

EDAExtension 570ppy

Neg

otia

tions

Construction10years

A Summit Conferencebetween the USA and the USSR

Management Advisory CommitteeITER Physics Committee

Voluntary Physics Activities

Director General

ITER Council

Joint Central Team

PhisicsＲ＆Ｄ

Design

　　 　 　

(until July 1999)

NakaSan Diego GarchingDesign Integration In-VesselOut-Vessel

(until July 1999)

Design IntegrationBuildingFusion Safety R&D Coordinationetc.

SuperconductingMagnetPower SupplyTritiumRemote Handlingetc.

DivertorBlanketVacuum Vesseletc.

Technical Advisory Committee

HTL HTL HTL HTL

Task Agreement

JA EU RF US

EDA: organization

World-Wide Cooperation in ITER/EDA

•Efficient use of high speed link and information technology•Multi-national engineering and industries

Garching

Design Center(St.Petersburg)

Naka San Diego

(until March 1999)

Detailed Technical Objectives

Plasma Performance:• to achieve extended burn in inductively driven plasmas with the ratio of

fusion power to auxiliary power injected into the plasma Q>10 with aninductive burn duration between 300 and 500s,

• to aim at demonstrating steady-state operation using non-inductivecurrent drive with Q>5,

• Controlled ignition should not be precluded.

Engineering Performance and Testing:• demonstrate availability and integration of essential fusion

technologies,

• test components for a future reactor,

• test tritium breeding module concepts; with a 14MeV neutron averagepower load on the first wall > 0.5 MW/m2 and fluence 0.3 > MWa/m2,

• the option for later installation of a tritium breeding blanket on theoutboard of the device should not be precluded.

I T E R

Fusion Power : 500 MW

Q Value : >10

Major Radius : 6.2 m

Minor Radius : 2.0 m

Plasma Current : 15 MA

Magnetic Field

Maximum : 11.8 T

Plasma Center: 5.3 T

Major Specifications

0m 10m 20m 30m

Blanket

Super-conducting Magnets

Plasma

Vacuum Vessel

Cryostat

Divertor

ITER Technology DevelopmentITER

7 Large Technology R&D's

CS Model Coil

Divertor Cassette Remote Handling

Divertor Cassette TF Model Coil

Blanket Module

Blanket Module Remote Handling

VV Sector

Central Solenoid Model Coil (1)

Cu Dummy

SC Cable

Jacketing

CS Insert

TF Insert

Russia Japan EU USA

Outer Module

Jacket

Inner Module

Cabling

Conductor

Winding

Assembling

International Collaboration

Central Solenoid Model Coil (2)

Achieved technology

TF Insert (Russia)Nb3AI Insert (Japan)CS Insert (Japan)

Inner Module (USA)(1st~10th Layer)

Outer Module (Japan)(11th~18th Layer)

Supporting

Structure (USA)

BufferZone

SupportingStructure

TF Insert

Conductor Joint

Main ParametersInner Diameter:

Outer Diameter:Coil Height:

Coil Weight:Operating Current:

Magnetic Field:

1.6m

3.6m

2.8m

110ton

46kA

13T

1m

Expert Groups on ITER Physics R&D

Energetic Particles, Heating, and Steady State Operation

1999 – 2001Confinement and Transport Physics

1994 – 1999Transport and Internal Barrier Physics

Confinement Database and Modeling

Confinement Database and Modeling

Edge Database and Modeling Edge and Pedestal PhysicsScrape-Off Layer and Divertor Physics

Scrape-Off Layer and Divertor Physics

Disruptions, Equilibrium Control and MHD

MHD, Disruptions and Control

Fast Particles, Heating and Current DriveDiagnostics Diagnostics

Operation Region of ITER

0

1000

800

600

400

200

0.7 0.8 0.9 1.0 1.1 1.2 1.3

Fus

ion

Pow

er(M

W)

Ploss/PLH=1.3

ne/ nG =1βN=2.5

Confinement Improvement Factor (HH)

ne/nG

Q=Fusion Power/Auxiliary PowerIp=15MA

Enhanced Operation Region

1000

800

600

400

200

0.7 0.8 0.9 1.0 1.1 1.2 1.3

Fus

ion

Pow

er(M

W)

0

Ploss/PLH=1

ne/nGW

=0.8

No

Sol

utio

n n e/n G

W=1

.0

Ip=17MA, Q=50

βN =2.5

βN =2.0

Confinement Improvement Factor (HH)

Long Pulse/Steady State Operation of ITER

0

2 0 0

4 0 0

6 0 0

8 0 0

1 0 00

0 . 7 0 . 8 0 . 9 1 1 . 1 1 . 2 1 . 3 1 . 4 1 . 5

5000s

n e/n G

W=1

.0

VLO

OP

=0.0

4V

1250s

n e/n GW

=0.8

Q=5Steady state

Q=5

V LOO

P=0

.01V

V LOO

P=0

V

VLO

OP

=0V

ss ssβN=3.0

βN=2.5 βN=3.5

Fus

ion

Pow

er (

MW

)

Confinement Improvement Factor (HH)

Q=10Steady state

Reference Schedule of ITER Project

II III IVI II III IVI II III IVI II III IVI II III IVI II IIIIV I II III IV

1999 2000 2001 2002 2003 2004 2005 2006

I

▼

Signing of Agreement

II III IVI

Joint Implementation

▼▼▼

▼

ODR FDR FR

EDA

Coordinated Tech.Activities

SWG EX Negotiations DomesticProcedure

Site Offers

Special Committee on ITER Project (Japan)

ODR:Outline Design ReportFDR:Final Design ReportFR:Final Report

SWG:Special Working Group EX:Exploration

COEDA:Construction, Operation, Exploitation Decommission Activities

Establishment of ILE (ITER Legal Entity)

FRANCECadarache

CANADAClarington

JAPANNaka, Rokkasho, Tomato

Rokkasho

FRANCE

Tomato

Rokkasho

Naka

CANADA

Summary

• Through the collaboration among the JCT andEDA partners, the design and R&Ds has beensuccessfully conducted.

• The technical basis toward the construction hasbeen established.

• Negotiation among EU, JA, RF and Canada hasbeen started aiming at the signature by the endof 2002.

Now,we are ready for ITER.