iter, overview - ippiter, overview. songtao wu . institute of plasma physics, cas iter international...

ASIPP, Hefei, August 18, 2009

ITER, Overview

Songtao WU Songtao WU

Institute of Plasma Physics, CASInstitute of Plasma Physics, CASITER International Organization

18 August 2009


ITER, OverviewITER, Overview

1. Background and Objectives2. ITER Tokamak and Major Systems3. Nowadays Situation


1985

•

At the Geneva Superpower Summit Meeting on 21st

November, a proposal was made by the then Soviet Union to build a next generation tokamak experiment on a collaborative basis involving the world's four major fusion programmes in Europe, Japan, Soviet Union, and USA.


1986-1988 - Discussion and Negotiation•

The ensuing discussions resulted in the establishment of a collaboration under the auspices of the IAEA known as ITER - the International Thermonuclear Experimental Reactor - and also meaning "The Way" in Latin.

•

Representatives of the four parties developed a detailed proposal for cooperation on the Conceptual Design Activities (CDA) for ITER.

1988-1991 - (CDA) Conceptual Design Phase•

Start of common activities among EU,RF, USA and JA. Selection of machine parameters and objectives

•

The ITER CDA began in April 1988 and were successfully completed in December 1990.


1992-1998 - (EDA) Engineering Design Phase•

In July 1992, in Washington D.C., the four Parties signed an Agreement under the auspices of the IAEA, which established EDA of ITER.

•

Developed design capable of ignition - large and expensive.

1998 – USA withdrew•

By the end of its 1999 fiscal year, USA withdrew.

•

At the time of the FDR’s acceptance, the Parties recognized that they might be unable, for financial reasons, to construct the device.

•

A Special Working Group (SWG) was set up for reducing the cost by reducing ITER’s technical objectives and decreasing the technical margins while maintaining the overall objective of ITER.


1999 - 2001•

The EDA was subsequently extended to July 2001.

•

New design: moderate plasma power reduction at about half the cost.

•

The complete and fully integrated documentation of the ITER design to make a decision on construction was completed and approved by the ITER Council in July 2001.

1998 2001Plasma major radius (m) 8.1 6.2

Plasma half width at mid-plane (m) 2.8 2.0

Plasma elongation (95% flux surface) 1.6 1.7

Toroidal magnetic field on axis (T) 5.6 5.3

Nominal maximum plasma current (MA) 21 15

Nominal fusion power (MW) 1500 500

Nominal inductive pulse length (s) >1000 >400

Average neutron wall load (MW/m2) ~1.0 0.57

Estimated direct construction cost (1989 US $) 5460 3013


2001 - 2002•

Coordinated Technical Activities (CTA) underpinning Negotiations on the joint implementation of ITER.

•

The CTA terminated in December 2002, the CTA work being continued under ITER Transitional Arrangements (ITA).

•

By the middle of 2002, four possible sites for ITER had been proposed, at Cadarache, Vandellòs, Rokkasho-mura and Clarington.

ITER Candidate Sites

FranceSpainCanada Japan


2003-2004•

In January 2003 China joined ITER as a full Party, and the USA rejoined in February 2003. The Republic of Korea joined ITER in June 2003.

•

Cadarache, France selected as European candidate site on November 26th, 2003.

•

Deadlock on site decision - December 20th, 2003. •

Canada left ITER – Jan. 7th , 2004.

2005•

Cadarache was selected as ITER site on 28, Jun. 2005.

•

Final NSSG/N meeting was held in Jeju, Korea from 1 to 9 Dec. 2005. The India joined ITER.


2005•

The ITER Joint Work Site in Cadarache was inaugurated on Thursday 15 December 2005 by a ribbon-cutting and olive- tree-planting ceremony, in the presence of regional politicians and representatives of the embassies and consulates of the ITER Parties.


2006•

“ITER Joint Implementing Agreement (JIA)” initiated in Brussels in May 2006.

•

On 21 Dec. 2006, the signature of the JIA took place at a ceremony at the Elysée Palace in Paris and was hosted by the President of the French Republic M. Jacques Chirac and by the President of the European Commission, M. José Manuel Durão Barroso.


2007•

On Wednesday, 24 October 2007, the ITER Organization formally entered into force.

•

On Tuesday, 27 November 2007, for the first time in the history of the new International Organization the ITER Council convened in the Château de Cadarache, France.


On 24 October 2007, following ratification by all Members, the ITER Agreement entered into force and officially established the ITER Organization.


2008•

The (IAEA), Vienna, Austria, and the ITER Organization sign a Cooperative Agreement on 13 October 2008 to enhance research on fusion and strengthen the working relationship between the two organizations.

2009•

Work on the impressive ITER platform comes to an end in April, 2009. The platform is now ready to receive the scientific buildings and facilities of the ITER project.


ITER ObjectivesProgrammatic•

Demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.

Technical•

Demonstrate extended burn of DT plasmas, with steady state as ultimate goal.

•

Integrate and test all essential fusion power reactor technologies and components.

•

Demonstrate Safety & Environmental acceptability of fusion.

Strategic•

A single device answering, in an integrated way, all feasibility

issues needed to define a subsequent DEMO except for material development and to provide low activation and larger 14 MeV

n-resistance at least for in-vessel components.


Project Costs

Magnet SystemsCryogenie

& VesselInternals

Others

Power SuppliesDistribution &

& DiagnosticsCODAC

Cooling WaterSystems

Buildings

Assembly & R/H Cryostat & TS

Construction Cost:

Total procurement value : 3021 kIUA

Staff: 477 kIUAR&D: 80 kIUATotal amount: 3578 kIUA (5365 Mil € / 2008 )Overall contingency : 358 kIUA ( 10% of total )

Operations Cost for 20 years : 188 kIUA / year

Deactivation and Decommissioning: 281 + 530 kIUA

IUA: ITER Units of Account1 IUA is equivalent to 1 kUS$ in 1998

European Union (5/11)

RF(1/11)CN

(1/11)KO

(1/11)JA

(1/11)IN

(1/11) US(1/11)


ITER Main ParametersTotal fusion power 500 MW (700 MW)Q = fusion power/auxiliary heating power ≥10 (inductive)Average neutron wall loading 0.57 MW/m2 (0.8 MW/m2)Plasma inductive burn time ≥ 300 s Plasma major radius 6.2 mPlasma minor radius 2.0 mPlasma current (inductive, Ip ) 15 MA (17.4 MA)Vertical elongation @95% flux surface/separatrix 1.70/1.85Triangularity @95% flux surface/separatrix 0.33/0.49Safety factor @95% flux surface 3.0Toroidal field @ 6.2 m radius (max. conductor) 5.3 T (≤12 T)Plasma volume 837 m3

Plasma surface 678 m2

Installed auxiliary heating/current drive power 73 MW (100 MW)


Central Solenoid

Toroidal Field Coils

Poloidal Field Coils

Machine Gravity Supports

Blanket Modules

Vacuum Vessel

Cryostat

Port

Divertor

Magnet Supports

ITER Tokamak Machine 29 m high × 28 m dia. & ~23000 tons

Correction Coils

Plasma


Facts- 48 superconducting coils - Operation temperature – 4.5 K- ~ 187 km of conductor- 11.8 T (peak TF field)- 68 kA (peak current)- Stored energy – 51 GJ- ~ 9800 tons

ITER Magnet System Status

6 PF Coils (EU & RF)

CS Coils – Stack of 6 (US)

31 Feeders (CN)9 Pairs of Correction Coils (CN)

18 TF Coils (EU & JP)


TF Coil TF Coil –– Mass ComparisonMass Comparison

Mass of (1) TF Coil: 16 m Tall x 9 m Wide, ~360 t

Boeing 747-300 (Maximum Takeoff Weight) ~377 t

http://image067.mylivepage.ru/chunk67/1488486/1086/Boeing 747-31 1.jpg


ITER Magnet Field

ITER magnetic Field ~10 Tesla or 200,000 x Higher

Earths Magnetic Field ~ 0.5 gauss or 0.5x10-4 Tesla


VV & In-vessel components mass: ~8000 t19.4 m outside diameter x 11.3 m tall

Eiffel Tower mass: ~7300 t324 m tall

(Completed 1889)

ITER Vacuum VesselFacts - First safety barrier for ITER- SS 316 LN-IG- ~5300 tons (VV, ports, shielding only)- 19.4 m (63 ft) torus outer diameter- 11.3 m (37 ft) torus height


Divertor

In-vessel Components – Blanket & Divertor

Blanket Vacuum Vessel

Port Plug


The blanket and diverter

are needed to …

The blanket

-

Provide shielding for the superconducting coils

-

Provides high heat flux component to face the plasma (protect the VV)

The divertor

-

Provide shielding for the superconducting coils

-

Extract heat and helium ash form the plasma (allows a high performance plasma)


Blanket System

Facts• 440 blanket modules at ~4 ton each• ~40 different blanket modules

Issues• Thermal and mechanical loads very high• Manufactured by 6 Parties• QA/QC of components (at 6 Parties)• Remote handling


Divertor SystemFacts- 54 Divertor assemblies- 4320 Heat flux elements

Issues• Thermal and mechanical loads very high• QA/QC of components (at 6 Parties)• Remote handling


CryostatThe magnet system is installed inside a cylindrical cryostat, held under vacuum. This, plus thermal shields, minimizes the heat in-

leak to the magnet system from the warm components and the surrounding environment .The Cryostat is 29 metres tall and 28 metres in diameter.The Cryostat is 29 metres tall and 28 metres in diameter.

Jefferson Memorial (Washington DC)~29 m Tall (floor to top of dome)


Machine Assembly

TF Coil / Sector Assembly TF Coil / Sector Assembly ~1400 ton ~1400 ton

TokamakTokamak and Assembly Buildingand Assembly Building

ASIPP, Hefei, 18 August, 2009

Transfer Cask Systems (EU+CN)Blanket RH System (JA)

Many Remote Handling SystemsMany Remote Handling Systems

1

2

456

7891 0

3θ1

θ2θ

3θ4

α1α

2α3

θ5

+/- 90°

+/- 100°

+/- 90°

+/- 180°

0°180°

+/- 180°

+/- 90°

+/- 90°

0 6200mm

0 4500mm

limits

Pitc h 5

1 0

Roll 3

9Pitc h 4

8Roll

27

Pitc h 3

6Roll

15

Pitc h 2

4Pitc h 1

3Tra nsla tion

2

2Tra nsla tion

1

1Na me

D O F

In-Vessel Viewing System

Multi Purpose Deployer

Cassette Toroidal MoverHot Cell RH Equipment


Initially: 73 MW Upgrade: possibility for 130 MW

ITER Heating & Current Drive


Neutron Beam InjectionUnit H DT

NB H&CD injection power MW 27 33 - 50

NB H&CD beam energy MeV 0.87 1

NB H&CD beam on time s 3600 3600


Electron Cyclotron Heating & CDSCOPE

f= 170 GHz, 20 MW : heating & current drivef= ~127 GHz, 3 MW: plasma breakdownEquatorial Launcher :1Heating for Q>10 and L-H transition Current drive for Steady State operation, Upper Launcher : 4Stabilisation of MHD instabilities

Start-up gyrotrons

170 GHz gyrotrons

Upper launchers

Equatorial launcher

Corrugated waveguide

27 gyrotrons ( each to 2 MW )


Straps

Front Housing

Removable Vacuum Transmission Line

Core Conductors

Vacuum Windows

Equatorial IC LauncherComposed of 24 straps grouped in 8 triplets (only one visible here)

SCOPEf= 40-55 MHz, 20 MW : Heating & current driveEquatorial Launcher :1Heating for Q>10 and L-H transition Current drive for Steady State operation ( 1 MA ) Assist in Plasma Startup

Ion Cyclotron Heating & CD


Cryogenic System

•

LHe

cryoplant:

65 kW equivalent @ 4.5 K–

Cooling of the superconducting magnet system, HTS current leads

–

Cooling of cryo-pumps with high regeneration frequency and small users

•

LN2

cryoplant:

1300 kW @ 80 K–

Thermal shielding, LHe

cryoplant

pre-

cooling

•

Helium inventory:

24 t

Cryoplant

Cryo distribution boxes and cryolines


DiagnosticsAbout 45 different diagnostic systems will be installed around the ITER tokamakThree categories: •

necessary for machine protection or basic control•

necessary for advanced performance control •

for evaluating the plasma performance and for understanding important physical phenomena


ITER I&C


Hot Cell blanket & divertor RH refurbishment area layout

Divertor cassette RH refurbishment & testing equipment

Hot Cell Remote Handling

The hot cell provides space and handling facilities for the reception, dispatch, decontamination, storage, repair, refurbishment and testing of highly radioactive and, or contaminated in-vessel components and materials (divertor cassettes, blanket modules, and other in-vessel component such as diagnostics and port plugs).


Fuel Cycling•

ITER will be the first fusion machine fully designed for Deuterium-Tritium operation.

•

Commissioning will happen in three phases: Hydrogen operation, followed by Deuterium operation, and finally full Deuterium-Tritium operation.


Tritium Breeding•

Tritium in the Earth's crust is limited, estimated currently at twenty kilos.

•

A second source of Tritium fortunately exists: Tritium can be produced within the tokamak when neutrons escaping the plasma interact with a specific element — Lithium — contained in the Blanket.

•

ITER will provide a unique opportunity to test mockups of breeding blankets, called Test Blanket Modules.


Present Structure of the ITER Organization


Staffing Status

• By the end of July 2009, IO has a total of 391 staff, including 351 Direct Employed Staff, 35 Seconded staff and 5 Post-Doc

• 38 temporary staff, 9 Visiting Researchers.

Staff by Members by the end of June, 2009:

Total: 391

CN: 15

EU: 257

IN: 23

JP: 28

KR: 18

RU: 23

US: 27Status of Professional Staff as of end June 2009

EU 65.7%

CN 3.8%US 6.9%RU 5.9%

KR 4.6%

JP 7.2%

IN 5.9%


ITER Staff Group Picture in May 2009

ASIPP, Hefei, August 18, 2009 1

ITER Construction Site (ITER Construction Site (FebFeb. 2009). 2009)


ITER ITER Site after ConstructionSite after Construction

Tokamak Hall Power Supply

Permanent Office Buildings

Parkings

32 Buildings, 180 hectares10 years of construction20 years of operation

Present HQ Building

To Aix

Hot Basin & Cooling Tower

Control Building Magnet AD/DC Converter

Site Services Building

Tritium, Vacuum, Fueling & Service Building

Cryoplant, PF Coil Fabrication & Emergency Power Supply Buildings

Hot Cell Building


Itinerary of ITER ComponentsITER Site

Itinerary of ITER ComponentsItinerary of ITER Components

演示者

演示文稿备注

THE objectives set out for ITER are basically two: ONE: to obtain and study a plasma where the alfa particle heating is dominating all other forms of heating. ITER will operate with a value of capital Q greater than 10. The fusion power in ITER will be about 500MW, the input power about 50MW. And TWO: it has to integrate the technology required for future use of fusion as an energy source


• Project Management– Tight schedule and budget– Limited resources– New organization– 7 Party coordination

• Design and Procurement– Complex design, requirement,

& interfaces– Severe QA / QC requirements– Complex procurement split– >90 procurement packages

• Superconducting magnets– Unprecedented size of the

superconducting magnets and structures

– High field performance ~12T

Why is the design of the ITER machine so challenging?

•Plasma facing components– >10 MW/m2 steady heat flux– >10000 cycles

•Remote maintenance (very complex)

•Vacuum and Tritium technology– Active recycling of tritium– Test of lithium blankets

•Cryogenic technology

•Heating and current drives– ~ 100 MW continuous– Neutral particles accelerators up to 1 MeV– Ion cyclotron, electron cyclotron

And others…


First Plasma planned in the end of 2018

2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020

“Permis de Construire” Start Tokamak

Assembly Complete Tokamak

Core Construction

Issue VV PAs

1st

VV Sector at Site Last VV Sector at Site

2018 First PlasmaMinimal internal vessel components

First Plasma

Tokamak

Basic Machine

ITER Construction

Issue TF Coils PAs

1st

TF Coil at Site Last TF Coil at Site

Buildings & Site

Tokamak

Complex Excavations

Tokamak

Building Construction

Site Leveling

Tokamak Bldg 11 RFE

Tokamak

AssemblyTokamak

Basic Machine Assembly

Ex Vessel AssemblyIn Vessel Assembly

Start Torus Pump Down

Start Install CS Start Cryostat Closure

Pump Down & Integrated Commissioning

Start Assemble VV

Current Date

Issue PF Coil PAs

1st

PF Coil at Site Last PF Coil at Site

Tendering process


The Way to the Future…

iter, overview - ippiter, overview. songtao wu . institute of plasma physics, cas iter international...

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