1

Summary　 onITER activities & Fusion Technology

Masahiro SEKIJAEA/RIST

S/1-5S/1-5

Contributors:T. Nishitani, Y. Kamada, M. Shimada, K. Okuno, P. Libeyre, K. Ezato, M. Gasparotto, J. Chen, X. Liu, M. Hanada, K. Sakamoto, A. Costley, A. Donne, M. Enoeda, Y. Wu, L. Boccaccini,B.G. Hong, S. Sato, U. Fischer, H. Tanigawa, N. Baluc, C. Petersen, H. Horiike, T. Fujita, M. Matsukawa, K. Tobita

21st IAEA Fusion Energy Conference- Summary Session

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Contributions to ITER Design and Technology

Total 68 papers were presented incl. ITER evening session

Overall status and schedule:6

Magnet:4

Physics & Control:21

RF technology:9

NB technology:4

Diagnostics:9

Fueling & TritiumTechnology:4

In-vessel components:11

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Contributions to Fusion Technology

Total 67 papers were presented including 2 overviews.

Overall status of new machine:11

Magnet:5

Control:3

Heating:4

Blanket & Neutronics:14

Plasma Facing components:7

Reactor design:11

Material & IFMIF:10

ICF technology:2

4

ITER Status and Preparation

The ITER Agreement will be signed on Nov. 21st . (Ikeda) The main engineering challenge of ITER is to produce it on time and within

budget . (Holtkamp) The site license, to be given for the initial design, should be maintained end

uring design changes during construction. Detailed design review is on-going. EFDA, EURATOM-CEA and other EU fusion labs are working on safety lice

nsing, technical studies and socio-economy aspects. (Gasparotto)

The ITER building

5

ITER Physics

For inductive and steady-state operation in ITER, Phys. Research achieved remarkable progress, and Remaining Key Physics Issues have been identified and requirements have been clarified.(Stambaugh)

Example: Resistive Wall Mode : Critical rotation identified (~ 0.3% of Alfven velocity) (JT-60U , DIIID) and design of control coil is underway.

Plasma Stability (RWM, NTM, disruption mitigation, ELM mitigation, AE),PWI and wall materials, Steady state Hybrid operation scenarios and required heating capability)

Edge pedestal ( Kamada) and Divertor (Lipschultz) Physics research has clarified the structure and dynamics of the complex system. Remarkable progress seen in ELM physics:ELM cycle has been clarified from the core,pedestal, SOL and Divetor.ELM mitigation techniques in ITER have been designed.Needs for Rotation Control were emphasized.

ELM control Coils

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ITER Operation & Control

Electromagnetic (EM) and heat loads at disruptions are analyzed with new guidelines. The margin in EM loads is not large, indicating the need of accelerated efforts in disruption control and design (Shimada).The “search and suppress” scheme of neoclassical tearing modes has been developed with direct relevance to ITER (Humphreys) .

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Superconducting Magnets

Central SolenoidConductor: JAWinding: US

Major successes have been obtained: LHD magnets have been operated for eight years (Imagawa), EAST magnets have been commissioned (Weng), KSTART magnets have been manufactured and assembled (Park).

In ITER (Okuno, Libeyre):Procurement sharing of the ITER magnets have been defined and procurement prepar

ation has been started including fabrication trails at full scale level.Several suppliers in Japan and EU have satisfied advanced Nb3Sn strand requirement

s. The conductor performances have still to be improved and confirmed.

12.5 m

4 m

12.5 m

4 m

14 m14 m

TF CoilsConductor: JA, EU, KO, RF,US, CNStructures: JAWinding: JA, EUCasing: JA, EU

High Tc superconductor is being studied for future fusion devices (Janeschitz).

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ITER VV & In-vessel Components

• In VV and in-vessel components, several detailed design improvements are being pursued to raise reliability, to improve maintainability and to reduce the cost.

• R&D activities are continued to confirm the design validity and to develop alternative fabrication techniques to increase reliability and to save cost, such as VV sector, joining of Be tiles to FW panels.

• A divertor integration prototypes were fabricated to qualify the manufacturing process, assembly procedure, and hydraulic test.

Full sizeVV mock-up (poloidal sector):Full sizeVV mock-up (poloidal sector): Full scale Divertor componentsFull scale Divertor components

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ITER Diagnostics

A comprehensive diagnostic system (45 individual systems) is being designed. And engineerign design of port pugs with complicated stuructures is being progressed (Costley IT/1-5).

A number of R&Ds such as irradiation effects on diagnostic components, and innovative diagnostics development such as -particle measurement have been carried out coodinated by ITPA (Donne, Murari, Orsitto, Hellerman, Litnovsky,etc.).

Requirements

Chosen systemsand design

Integration and implementation

Assessment relativeto requirements

Magnetics OpticalMicrowave

Fusion

Products

Bolometry

SpectroscopyProbes

~100 - 150 techniques

Suitability in ITER environment; expectedperformance; reqmsfor space, etc,

Measurement priorities;combination with othersystems; engineering constraints, etc

R&D

Requirements

Chosen systemsand design

Integration and implementation

Assessment relativeto requirements

Magnetics OpticalMicrowave

Fusion

Products

Bolometry

SpectroscopyProbes

~100 - 150 techniques

Suitability in ITER environment; expectedperformance; reqmsfor space, etc,

Measurement priorities;combination with othersystems; engineering constraints, etc

R&D

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MAMuG836 keV,146A/m2 (0.2 A) H- (JAE

A: Hanada)

SINGAP 727 keV, 120 A/m2 (0.02A) D-(Ca

darache: Bonicelli)

Development and Design of NB system in ITER

Ion Source R&D

Accelerator R&D

Arc ion source 21s, 3.2 MW D0 injection

(JAEA: Hanada)Improvement of beam uniformity

(JAEA: Hanada)

RF ion source600s, 3A （ 160 A/m2), (Garching:

Franzen )Test in a half-scale of the ITER so

urce.(Garching:Franzen )

HV bushing R&D

A full-size ceramic insulator(JAEA:Hanada)

Design of the ITER NB system

-Design of a full-scale test facility-Design of the alternative concepts for RF ion source and SINGAP

(ENEA:Antonio)

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Progress of EC Technology (8 papers)

EU Coaxial 2MW Gyrotron

Upper port launcher (EU)

Equatorial port launcher (JA)

Gyrotron 170GHz for ITER (Piosczyk, Litvak, Sakamoto) 140GHz for W-7X (Erckmann, Gantenbein) 2 Frequency Gyrotron for ASDEX (Litvak)ITER Launcher Upper port (Heidinger, Saibene, Henderson) Equatorial port (Sakamoto)

Upper port Launcher: Proposal of front mirror steering for effective NTM control

Gyrotron: Remarkable progress for ITER1MW gyrotron :0.82MW/10min./56% 0.6MW/1hour /2.1GJCoaxial gyrotron: Fabrication finished. to be tested at test stand of CRRP (EU joint project)

0

0.2

0.4

0.6

0.8

1

1.2

10 100 1000 104

Pulse Duration (s)

Ou

tpu

t Pow

er

(MW

) ITER

~2003

2005

2006/9

56%

2004

2006/8

ITER 170 GHz Gyrotron:

(RF)

140GHz (EU)

JA

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Blanket & Neutronics (ITER-TBM)

There are two kinds of blanket concepts, solid breeder (Li4SiO4, Li2TiO3) concepts and liquid breeder (LiPb, Li) concepts with reduced activation ferritic/martensitic steels. In this conference, China, EU, Japan and Korea presented their proposing test blanket designs and R&D achievements.• Design of test blanket and integration in ITER systems are showing significant progress, including safety evaluation for the ITER Preliminary Safety Report.• R&D on the technologies for material and module fabrication, ancillary systems is showing steady progress toward installation from day 1st of ITER operation.

Test blankets are the prototypical breeding blanket modules to be tested in real fusion environment in ITER. Test blanket testing in ITER is an essential and most important milestone toward DEMO.

JapanChina KoreaEU

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Blanket & Neutronics (Neutronics)

Detector

Heterogeneous geometry

Li2O pebble (１mm)

F82H(1.8mm) DT neutron source

Beam line

Be block(100mm)

For the first time, TPR distributions have been measured using pebble bed mockup by JAEA FNS. (Sato)

Also TBM mock-up experiment of the HCPB breeder blanket was performed in EU,(Fischer)

CAD model of ITER 40 ° torus sector (CATIA V5)

Conversion algorithms from CAD data to MCNP(neutron transport code) geometry data were implemented into McCad (FZK) and MACAM (IPP China). (Fischer) (Chan)

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New Experimental Machine (Tokamak)

EAST (China)R = 1.7m, a = 0.4m, Bt = 3.5T, Ip = 1MA.First plasma on September, 2006.First full superconducting tokamak.

SST-1 (India)R = 1.1m, a = 0.2m, Bt = 3.0T, Ip = 0.22MA.Fabrication and assembly completed.SC magnets cooled down for charging tests.

Four superconducting tokamaks in Asia

EAST

JT-60SA (Japan/EU)R = 3.06m, a = 1.15m, Bt = 2.7T, Ip = 5.5MA.Conceptual design is in progress.Fabrication will be started in 2007.

KSTAR (Korea)R = 1.8m, a = 0.5m, Bt = 3.5T, Ip = 2MA.Assembly will be finished and commissioning

will be started in middle of 2007. KSTAR

SST-1

Both DN and SN configurations are possible in all four tokamaks

JT-60SA

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New Experimental Machine (Stellarator)

Plasma vessel

Central support ring

20 Planar coilsnominal current16kA @ 4K @ 6T

50 Non-planar coilsnominal current18.2kA @ 4K @ 6.7T

Machine support

Wendelstein 7-X (Germany)A fully optimized low-shear stellarator of th

e Helias type with NbTi superconductor coils.

Importance of cold testing of at least one coil of each type, followed by tests in Paschen conditions, is recognized.

NCSX (USA)A compact stellarator with 18 modular cop

per coils.Fabrication of vacuum vessel completed.5 modular coils completed with +-0.5 mm a

ccuracy.On schedule for first plasma in July, 2009.

Current Center Shifts Relative to Targets for C1 thru C5

Radial

-1.000

-0.750

-0.500

-0.250

0.000

0.250

0.500

0.750

1.000

0 20 40 60 80 100

Poloidal Location by Clamp#

Sh

ift,

mm

+0.5mm

-0.5mm

modular coil

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RAFM steels remain presently the most promising structural materials for plasma facing components and breeding blanket applications: (Baluc)

– A great technological maturity has been achieved: qualified fabrication routes, welding technology and a general industrial experience are almost available.

– RAFMs, F82H and EUROFER97, are ready for ITER-TBM (Petersen, Tanigawa), but still remain some issues for DEMO application.

– Possible solution for those issues are suggested (Petersen, Tanigawa )– Needs of close discussions between designers and material scientists are indicated.

Fusion Material

Tempering effects :(Tanigawa)

Annealing the irradiated materials could recover the degraded mechanical properties.

Post-irradiation annealing effects :(Petersen)

As irrad.

As prep.

Post-irrad. annealed

(Tempering strength)

Tempering condition could suppress radiation effects on mechanical properties.

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IFMIF Project

The IFMIF-EVEDA (Engineering Validation & Engineering Design Activities) will be initiated as a part of the Broader Approach Project which is the EU-JA Bilateral Agreement (Matsuda, Matsui). IFMIF is regarded as a major element in the fusion roadmap (Matsui). Design of the target and test cell has been progressed (Heinzel). And R&D on the liquid Li flow target is carried out (Horiike).

New design of Li target backplatePicture of Li flow surface

Backplate alternative

deuterons Li

High flux module

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Reactor Design (Tokamak )

PPCS 1) Reactor concept (Tobita)

2) Divertor (Ezato)

• compact low-A DEMO with reduced-size CS

• potentially economic & low-A merit in design margins

1) Reactor concept (Maisonnier)2) Shield (Jordanova)3) He-cooled div. (Norajitra)4) Physics issues (Campbell)5) Transport & Stability (Pereverzev)

• 5 plant models based on different extrapolations (physics and materials)

• He-cooled divertor ~10 MW/m2

SlimCS

Demo-CREST

Physics & engineering issues (Hiwatari)

• proposed in-life upgrade strategy to bridge the gap between ITER and economic CREST

Ignitor

Physics design & technology (Coppi)

Neutron source

Assessment of transmutation reactors (Stacey)

SlimCS

Power Plants (EU)

DEMO (CRIEPI)

DEMO (JAEA)

Exp. reactor for physics study (Italy)

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Reactor Design (Helical and ICF)

1) Neutronics (Tanaka)2) Operation scenario (Mitarai)

FFHR2

ARIES-CS

Reactor concept (Najmabadi)

• Structure with three radial builds (shield-only / nominal BLK & shield / transition zone)• Plants that have similar size as tokamak <R> = 7-8 m

KOYO-F

• Progress in design rotary shutters for protecting final optics chamber design with cascade surface flow • Develpment in cooled Yb:YAG ceramic laser

1) Reactor concept (Norimatsu)2) Laser driver (Kawanaka)

KOYO-F

3D MC analysis

Laser plant design (Osaka U) Force Free Helical Reactor (NIFS)

Stellarator plant (UCSD)

Figure of ARIES-CS?

Chamber wall

• Developed 3-D Monte Carlo neutronics calculation system

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Summary Remarks

• ITER performance prediction, results of technology R&D and the construction preparation have been steadily progressing, which provide good confidence of ITER realization.

• Superconducting tokamak EAST achieved the first plasma just before the conference. Constructions of other new experimental machines have also shown a steady progress.

• Future reactor studies, most of advanced tokamaks, STs or Helical systems stress the importance of high beta, down sizing and steady state approach.

• Reactor technology in the field of blanket, especially ITER TBM program, and materials for demonstration power plant showed a sound progress in both R&D and design.

21st IAEA Fusion Energy Conference- Summary Session