A first study for assessing the surface temperature measurement of the ITER plasma facing components (PFC) was performed by IRFM in partnership with industry. Starting from a simplified 3D model of the ITER torus, it has allowed to obtain the first simulated images that an infrared camera located in an equatorial plan would see. The post treatment analysis of the simulated images shows that the collected flux on the camera is largely dominated by reflected flux leading to important errors over the temperature measurement.

Indeed, in the future machines like ITER plasma facing components have metal armors, complicating the interpretation of infrared measurements. The camera will not only receive the flux directly emitted by the PFC, but also signal due to multiple reflections. Therefore to find the temperature of the components one should be able to separate the signal coming from the source itself from the one coming from other sources through multiple reflections.

These studies rely on a Monte Carlo method that calculates the propagation of the radiation in a complex 3D environment. The result allows taking into account the precise geometry of the torus while simulating very accurately the interaction radiation-matter.

The next stage of this study will be to apply this model to the JET “metallic wall”, to compare the simulated results with the experimental ones. This is essential to define the operational specifications for future infrared diagnostics, for monitoring the plasma facing components, a very important point for ITER operation.

Simulated infrared pictures of ITER divertor and inside wall

In order to define the test procedures and the acceptance criteria during the manufacture of the poloidal field coil (PF) conductor of ITER, IO (ITER Organization) ordered the study, the design and the realisation of 2 samples to ENEA (Italy), in collaboration with CEA/IRFM. IO provided the raw conductor, the ENEA dealt with the “jacketing” and the manufacture of the lower box, the IRFM dealt with the realisation of the terminals and the instrumentation. The two teams worked in close cooperation, completing the preparation of the first sample, which was tested successfully on the test bench SULTAN of the institute Paul Scherrer located at Villigen (Swiss). The second sample should arrive at the CEA for finalisation at the beginning of June and testing on SULTAN at the end of June. In the frame of another ITER contract, the CEA also participates to the supervision and the analysis of the results of the tests of these samples. The tests carried out on the first sample indicate good performances and a temperature margin (with I = 35kA and B = 3.5T) approximately 0.1K higher than initially foreseen.

These good performances confirm the quality of the PF conductor design, as well as the validity of the work realised by the ENEA and IRFM teams during the manufacture and instrumentation stages of the sample. This constitutes an important and promising step on the critical path to qualify the ITER PF conductors.

Prototype conductor of ITER poloidal field coils

During the inspection of the inside of Tore Supra following the last experimental campaign, damages were discovered on an actively cooled protection facing the plasma, which could have caused to a water leak.

After reviewing all the plasma discharges in which these damages could have occurred and having visualised the films of the CCD camera observing the damaged zone, only one plasma discharge (n° 45565) is identified to be responsible. Correspondent at one experimental session of plasma heating study, this discharge does not present any particular anomaly, except during the last phase of extinction (end of the current decrease) where a disruption occurs. During this incident the camera shows an intense light on one of the damaged zones. A detailed study of this plasma indicates the creation of extremely energetic electrons during the very end of the current ramp-down, in a phase where plasma density and current are very weak. The simulation of the magnetic topology shows small plasma positioned at the top of Tore Supra vessel; the one of the energetic electron trajectories evidences the existence of a focusing point located behind the protections corresponding to one of the damaged zones. The observation of such melting points caused in the ultimate phase of the discharge, where plasma contains very little energy, is unexpected and contributes to increase the base of knowledge for the ITER reliable operation. Concerning Tore Supra, plasma controls will be modified to guarantee a sufficient plasma density, even during the current decrease phase, thus avoiding the acceleration of the electrons. 

The damaged component

New diagnostic DREVE (Vertical Reflectometry Diagnostic) based on radar techniques has recently delivered its first signals on Tore Supra. The association of this new system with an existing one, already on Tore Supra, will extend the correlation domain of the density fluctuations and their speeds to larger scales. This is a key ingredient to understand the behaviour of the turbulence and its link with the transport to obtain high performance plasmas with improved confinement  such in ITER or JET in H mode.

This new system, using radar techniques, is based on diffusion effects, due to the plasma density fluctuations generated by turbulence, on a probe wave. Various incidence angles of the probe wave correspond to various scales of the density fluctuations; whereas the temporal analysis of the retro-diffused wave gives the speed.

DREVE was designed and built within the framework of a close cooperation between the Laboratoire de Physique des Plasma (LPP, Ecole Polytechnique)  and the IRFM.

The new diagnostic DREVE in Tore Supra

2.7 MW coupled during 80 seconds to a Tore Supra stationary plasma, representing 223MJ of energy injected inside the plasma: it is the latest result recently obtained using the new passive active multijunction lower hybrid antenna recently installed on Tore Supra. Most of the plasma current (900A) has been non inductively driven, and the electron temperature has been increased by a factor of 2. Meanwhile, thanks to the efficient cooling of this new design, the temperature of the antenna and of its protection were kept very low (< 250°C).

This is an excellent omen to the next experimental campaign of Tore Supra that will benefit from the new capabilities brought by the completion of the CIMES project. It is also one more asset for considering the installation of a lower hybrid current drive system on ITER.

2.7 MW of hybrid power during 80s

The last results obtained on Tore Supra show that it is possible to mitigate the undesirable effects of disruptions using massive gas injection. It was shown that the lighter the injected gas is (helium), the quicker it penetrates into the plasma and the better is the damping of the energetic electrons (runaways) created during the disruption.

Disruptions are violent events; they occur spontaneously in tokamak plasma and consist of a brutal loss of the plasma balance and confinement leading to the end of the discharge. These events can be dangerous for the machine, via thermal loading of the plasma facing components, via electromagnetic forces leading to high mechanical constraints on the structures and via the generation of highly energetic runaway electrons that hits the walls. It is thus necessary to mitigate these deleterious effects.

Injection of a great quantity of gas into the plasma is one of the methods currently studied. Tore Supra is equipped with a massive gas injector making possible to test this technique, and with a large set of diagnostics to study it. In particular, a fast camera is able to follow the penetration of neutral gas into the plasma and to study its dynamic. (See picture) The main aim of these experiments is to understand the physical mechanisms leading to the mitigation of the disruption, to determine an optimal gas injection scenario (heavy and light gas mixture) that can be extrapolated to ITER. On present fusion devices, the plasma energy is relatively low, so that disruptions are only a minor inconvenience. However, on ITER, the plasma stored energy will be 100 times larger, and the consequences on the integrity of the machine will be much more severe. Disruption mitigation is thus a research programme of great interest for preparing ITER exploitation.

One of the March experimental runs of Tore Supra has been devoted to the training of students (within the master's degree Sciences de la Fusion) for enlarging their theoretical studies by some experimental works (see Le master Sciences de la Fusion.

A student team has been able to realise the first Tokamak experiment of the master "science de la fusion", a "premičre" greatly appreciated by these fusion novices. Coming from Nancy, Marseille and Ile de France universities, these students were gathered at Cadarache from February the 4th to march the 5th, thanks to the financial and logistic helps of the INSTN, the Cadarache centre and the IRFM.

They ended their stay by practicals using experimental platform of the Tore Supra tokamak. Three subjects have been proposed:
 -Qualification of plasma facing components
 -Measurements of the critical current inside a superconducting strand, using the BRENICE station.
 -Studies of the confinement regimes of ohmic Tore Supra plasmas.

The main goal of these experimental works was to initiate the students to the techniques used on fusion devices. Such initiation was really appreciated by the students and will be repeated in the future..

For further information:
Master's degree "Sciences de la Fusion"

Studients from the master's degree "Sciences de la Fusion" inside the control room of Tore Supra

Institut de Recherche sur la Fusion par Confinement Magnérique
Association Euratom-CEA
Annual report 2008

  Summary (17p, pdf, 3.6 Mo)

  Full report (139p, pdf, 7.5 Mo)

Contents:

            1 -  Introduction
            2 -  Tore Supra status
            3 -  Theory & modelling
            4 -  Experimental physics
            5 -  Technology developments
            6 -  Participation to W7X construction
            7 -  Broader approach activities
            8 -  Other activities
            9 -  Appendices
 

Fusion Technology : 2007-2008 activity report of the Association Euratom-CEA.

Executive Summary (38p, pdf, 2.4 Mo)

Full report (391p, pdf, 26 Mo)  

During Tore Supra experiments, plasma facing components are eroded, especially in high heat flux area. This eroded matter creates deposited layers which can in a first hand trap hydrogen, deuterium and tritium and in a second hand, become an issue for plasma operation. Manual cleaning of plasma facing component is performed inside Tore Supra but will be not possible on ITER. Therefore, new laser cleaning techniques are developed by Euratom-CEA in close collaboration with a CEA laboratory (DEN/DPC) and University (CNRS/LP3, Marseille).

On 06/02/2009, a demonstration of laser ablation techniques inside Tore Supra vacuum vessel has been performed, at room temperature and atmospheric pressure.

For further information:
Read the full document 
File Tore Supra

The first deployments of the Articulated Inspection Arm (AIA) inside Tore Supra under Ultra High Vacuum conditions (1,4.10-5 Pa ) and temperature (120°C) proceeded successfully on September 3rd, 2008.

After the vessel inspection, the experimental campaign of Tore Supra started without conditioning. This deployment is an important step toward the demonstration of remote handling inspection of the Iter components.

see the movie of the inspection

For further information:
Read the full document 
File Tore Supra

IOn April 1st 2008, a celebration took place at the Institute for Magnetic Fusion Research at the occasion of the 20th anniversary of the Tore Supra first plasma.

This was an excellent opportunity to gather several generations of physicists and engineers that had designed, built and operated Tore Supra. Before a convivial buffet, several staff of the Institute, either retired or in activity, recounted the Tore Supra adventure through various anecdotes that have marked them: industrialisation problems of NbTi superconducting cables; design of Tore Supra essentially conducted with drawing tables and slide rules; unbelief of foreign colleagues that a superfluid helium bath could properly cool down superconductors; atmosphere in the control room on the night between March 31th and April 1st 1988 with a scoop: the first plasma of Tore Supra probably happened on March 31th; evolution of power exhaust tools from the ergodic divertor to the toroidal pumped limiter; progress toward the 6 minutes duration discharge; the limiter deuterium loading campaign with its 5 hours of plasma concentrated on 10 operational days; the saga of the klystrons for current drive from the choice of the 3,7 GHz frequency up to the latest technological developments for the CIMES project.

Beneath the physics findings and the technological achievements, the human and team spirit aspects really shown through. Jean Jacquinot, former Head of the Institute and Y. Caristan, Director of the “Direction des Sciences de la Matičre” conveyed through remote participation their congratulations and encouragements to the Institute staff. Looking towards future prospects for Tore Supra concluded the presentations. The last word was given by R. Aymar, Tore Supra project manager and presently director of CERN who advised young scientists to always be able to keep a long ranging view on the future by always preparing the next step.

File Tore Supra

ICFRM conferences are held every two years in one of the fusion partner countries, alternating between Europe, Asia, and the USA. In this series, the 13th conference, organised by CEA, takes a special place in several aspects:
 - first major materials conference after the ITER site decision.
 - first ICFRM conference with major industrial exhibition (IBF/07)
 - first conference targeting synergy between fusion and fission materials.

Together, the two events, ICFRM and IBF, attracted about 1400 delegates from the scientific community and industry, as well as, 80 exhibitors. The two events were managed in a way that allowed maximum encounter between the participants, including free circulation of attendees between parallel industrial and material sessions.

Delegates from 33 countries attended the ICFRM conference, with new ITER partners marking an increased presence. For the first time, the conference welcomed delegates from several countries outside the ITER and IEA communities.

The scientific content of the two events was marked by: over 150 oral presentations, 500 posters, and 15 workshops. The number of abstracts received per topic reflected the evolution of the fusion programme. For instance, as we approach the ITER construction phase, the need for R&D work on conventional materials such as 316L(N)-IG steel has diminished, and more emphasis is placed on manufacturing of components and licensing.

Several session was dedicated to the effect of radiation on the behavior of functional and structural materials.  Furthermore, with the increasing availability of powerful computational tools, multiscale modelling of materials behaviour is rapidly advancing, as shown by a large number of papers in this sector.

The next ICFRM will be held in Satorro (Japan) on september 2009.

ICFRM13 website
IBF/07 website
 

With the ITER project, integrated modelling of plasma discharges is becoming an increasingly important objective, taking on its full scope and significance. Like any nuclear installation, ITER needs to have a simulator, i.e. software capable of predicting the complete evolution of a discharge, using control parameters. The existence and reliable operation of this simulator will play an important role in the safety of the reactor, for optimising the operation of the machine, and for programming campaigns of scientific experiments.

The CRONOS code (developed by the Euratom-CEA Association) is part of the small group of numerical suites on which the integrated modelling of thermonuclear plasmas is based at an international level.

Read the full document
 

Since 2003, the Euratom-CEA Association has developped a R&D program and the qualification of a poly-articulated arm called AIA (Articulated Inspection ARM) able to operate inside a Tokamak vacuum vessel.

The first deployments of the robot inside Tore Supra under atmospheric conditions proceeded successfully on September 13rd, 2007.

Read the full document 
 

For further information:
File Tore Supra

The diagnosis was officially accepted by the Operator of the JET in September 2007.

Read the full document 
 

For further information:
EFDA-JET website

Fusion Technology : Annuel Report of the Association Euratom-CEA. 
2006 activities
(June 2007) 

Executive Summary (45p, pdf, 4.2 Mo)

Full report (422p, pdf, 53 Mo) 

• pages 000-004 : Cover, contents, introduction (1.4 Mo)
• pages 004-043 : EFDA activities: plasma integration (2.3 Mo)
• pages 043-067 : EFDA activities:  vessel   (2.6 Mo)
• pages 068-102 : EFDA activities: plasma facing components   (9.3 Mo)
• pages 103-113 : EFDA activities: remote handling (1.6 Mo)
• pages 114-144 : EFDA activities: magnets (1.7 Mo)
• pages 145-211 : EFDA activities: breeding blanket (12.2 Mo)
• pages 212-253 : EFDA activities: structural materials  (4.1Mo)
• pages 254-257 : EFDA activities: IFMIF  (0.5 Mo)
• pages 258-270 : EFDA activities: safety  (0.7 Mo)
• pages 271-280 : EFDA activities: "Reactor" studies  (1.3 Mo)
• pages 281-285 : EFDA activities: ITER site studies  (0.5 Mo)
• pages 286-326 : EFDA activities: JET technologies activities (PFC, safety, rh,...)  (6.5 Mo)
• pages 327-329 : EFDA activities: heating project   (0.1 Mo)
• pages 330-330 : Underlying technologies  (0.03 Mo)
• pages 331-335 : Underlying technologies: vessel (0.5 Mo))
• pages 336-349 : Underlying technologies: plasma facing components   (2.6 Mo)
• pages 350-359 : Underlying technologies: remote handling (1.2 Mo)
• pages 360-361 : Underlying technologies: breeding blanket (0.5 Mo)
• pages 362-366 : Underlying technologies: structural materials (0.2 Mo)
• pages 362-366:  Underlying technologies: safety  (1.9 Mo)
• pages 377-394 : Inertiel Confinement  (0.8 Mo)
• pages 395-422 : Appendix    (0.2 Mo)

The so-called SATIR (Station d’Acquisition et Traitement InfraRouge) device is used to qualify plasma facing components. It strongly contributed to the success of CIEL components manufacturing. This device has been updated and is now able to test ITER components with increased performance.
Read the full document

SATIR device andv iew of 3 components during testing

A new diagnostic, so-called SURVIE (french acronym for Surveillance Rapide des Impuretés dans l'Ultra Violet Extręme) is in operation at Tore Supra. SURVIE is dedicated to plasma facing components security.

For further information: see the article diagnostic SURVIE,

SURVIE diagostic instaled on Tore Supra

The GYSELA code (GYrokinetic SEmi-LAgrangian) is able to model plasma turbulence in toroidal geometry. It uses original numerical methods. Such a 5D code needs a huge computing resources. Within the framework of the “Grand Challenge” project, first GYSELA runs have been done on the super computer Tera10, available at CEA/DAM (50 Tera-Flops, 8000 processors).

For further information: see the article Modélisation ŕ cinq dimensions de la turbulence dans un plasma de Tokamak,

GYSELA code simulation on the super computer Tera10

• Prologue

• Chapitre 1: Dans l'intimité de l'atome

• Chapitre 2: Du nucléaire au thermonucléaire

• Chapitre 3: Le démon est dans le plasma

• Chapitre 4: Le JET ou la fusion pour de vrai

• Chapitre 5: Les chauds et frods de Tore supra

• Chapitre 6: Y a-t-il une vie aprčs le pétrole ?

• Chapitre 7: Il faut sauver le programme ITER

• Chapitre 8: L'Europe choisi son site

• Chapitre 9: Six partenaires en quęte d'un accord

• Chapitre 10: Cadarache, un concentré d'énergies

• Chapitre 11: Toute une région mobilisée

• Questions

• Épilogue

• Annexes

• Bibliographie

For further information :

• Iter, le chemin des étoiles, édition EDISUD ,

Robert Arnoux et Jean Jacquinot,
2006, ISBN 2-7449-0615-8
Edition : EDISUD,

Fusion Technology : Annuel Report of the Association Euratom-CEA. 
2005 activities
(July 2006) 

Executive Summary (39p, pdf, 2 936 Ko)

Full report (432p, pdf, 45 772 Ko)

• pages 000-004 : Cover, contents, introduction (824 Ko)
• pages 005-038 : EFDA activities: plasma integeation(1 220 ko)
• pages 039-074 : EFDA activities:  vessel   (1 363 ko)
• pages 075-110 : EFDA activities: plasma facing components   (7 470 ko)
• pages 111-120 : EFDA activities: remote handling (1 147 ko)
• pages 121-160 : EFDA activities: magnets (2 908 ko)
• pages 161-220 : EFDA activities: breeding blanket 10 246 ko)
• pages 221-262 : EFDA activities: structural materials (3 402 ko)
• pages 263-284 : EFDA activities: safety  (858 ko)
• pages 285-296 : EFDA activities: "Reactor" studies  (720 ko)
• pages 297-300 : EFDA activities: ITER site studies  (373 ko)
• pages 301-306 : EFDA activities: design support  (204 ko)
• pages 307-310 : EFDA activities: JET/plasma engineering  (1 973 ko)
• pages 311-316 : EFDA activities: JET/plasma facing components (204 ko)
• pages 317-322 : EFDA activities: JET/safety  (2 355 ko)
• pages 223-334 : EFDA activities: heating project   (560 ko)
• pages 335-336 : Underlying technologies  ( ko)
• pages 337-338 : Underlying technologies: vessel (2 663 ko)
• pages 339-356 : Underlying technologies: plasma facing components  (2 663 ko)
• pages 357-366 : Underlying technologies: remote handling (959 ko)
• pages 367-370 : Underlying technologies: breeding blanket (2 663 ko)
• pages 371-380 : Underlying technologies: structural materials (2 020 ko)
• pages 281-394 : Underlying technologies: safety (432 ko)
• pages 395-421 : Appendix  (2 020 ko)

Visiting the ITER site in Cadarache with K. Ikeda, ITER Director..

The Chinese Premier Wen Jiabao visited the International Thermonuclear Experimental Reactor site situated in Cadarache. He also visited Tore Supra accompanied by Francois Loos, Minister for Industry, industrials and local politicians.

Visiting the ITER site in Cadarache

Visiting Tore Supra : Chinese Premier Wen Jiabao listens to explanations about plasma facing components  by Michel Chatelier, Head of the Research Controlled Fusion Department

During the 12th ITER negotiating meeting held inJeju  Korea, India was welcomed by the other partners as a full partner in the ITER project. The Delegations also welcomed Ambassador Kaname IKEDA, the newly Nominee Director-General for ITER.

Press released (from : http://www.iter.org )

For further information :
www.iter.gouv.fr

About ITER :
www.itercad.org
ITER

Visiting the ITER site in Cadarache

Commissioner Potocnik during his speech

President Jacques Chirac visited Cadarache to thank fusion staff that had made it possible to achieve the success of the Cadarache site to host ITER. President Jacques Chirac also visited the ITER site and Tore Supra device. Representatives of the French government and local politicians accompanied Jacques Chirac during the visit.

President Jacques Chirac's speech ( )

For further information :
www.iter.gouv.fr

About ITER :
www.itercad.org
ITER

Visiting Tore Supra : Michel Chatelier, Head of the Research Controlled Fusion Department presenting fusion technologies  to Jacques Chirac.

President Jacques Chirac during his speech.

An agreement has been signed on 28/06/2005f in Moscow between the ITER Parties to build ITER in Cadarache, France

See the "joint declaration" and the "joint attachment"

Fusion Technology : Annuel Report of the Association Euratom-CEA. 
2004 activities
(Juin 2005) 

Executive Summary (31p, pdf, 2 008 Ko)

Full report (332p, pdf, 25 905  Ko)

• pages 000-014 : Cover, contents, introduction (518 Ko)
• pages 015-022 : EFDA activities: plasma engineering  ( 960 ko)
• pages 023-048 : EFDA activities:  vessel   (1 742 ko)
• pages 049-072 : EFDA activities: plasma facing components   (1 858 ko)
• pages 073-086 : EFDA activities: remote handling (2 298 ko)
• pages 087-112 : EFDA activities: magnets (3 716 ko)
• pages 113-134 : EFDA activities: breeding blanket (2 330 ko)
• pages 135-170 : EFDA activities: structural materials (2 871 ko)
• pages 171-192 : EFDA activities: safety  (973 ko)
• pages 193-206 : EFDA activities: "Reactor" studies  (1 305 ko)
• pages 207-214 : EFDA activities: ITER site studies  (2 283 ko)
• pages 215-218 : EFDA activities: design support  (455 ko)
• pages 219-222 : EFDA activities: JET/plasma engineering  (1 333 ko)
• pages 223-226 : EFDA activities: JET/plasma facing components (277 ko)
• pages 227-238 : EFDA activities: JET/safety  (501 ko)
• pages 239-250 : EFDA activities: heating project   (560 ko)
• pages 253-266 : Underlying technologies: plasma facing components  (2 663 ko)
• pages 267-278 : Underlying technologies: remote handling (959 ko)
• pages 279-282 : Underlying technologies: breeding blanket (2 663 ko)
• pages 283-290 : Underlying technologies: structural materials (2 020 ko)
• pages 291-308 : Underlying technologies: safety (432 ko)
• pages 309-332 : Appendix  (2 020 ko)

The Council of EU Ministers (Competitiveness: domestic market, industry and research) decided unanimously to enlatge the Commission's negotiating Directives in order to reach an agreement to buidd ITER .

In particular, in order to ensure the widest possible international partnership, the Commission could include privileged partnership in the field of fusion materials and JT-60, a major Japanese fusion device.

If no official deadline has been mentioned, the European nations hope for a deal in a very near future.

Press Release (draf) Council of the European Union, Competitiveness (Internal Market, Industry and Research), 24/09/2004 (PDF) or WebSite of the European Council

Visiting the ITER site : the flag simulates the magnetic axis of ITER

Mr Jean Jacquinot presented the ITER site and the results of Tore Supra in the conference room of Tore Supra.

Mr François d’Auber answered questions and recalled engagements of the French government about the French candidature as well as the exceptional assets of the site of Cadarache. He also recalled decisions taken during the last Council of EU Ministers and in particular the negociation which are on going to reach an agreement to built ITER in Europe on the basis of an international cooperation as large as possible with at least three partners.

For further information :
www.iter.gouv.fr

About ITER :
www.itercad.org
ITER

Inside the
conference room

The minister
answering  questions

The Council of EU Ministers (Competitiveness: domestic market, industry and research) asked the European Commission to negotiate and prepare an agreement concerning construction in Europe, on the site of Cadarache, of the experimental fusion device ITER. The framework of this agreement will take place on the basis of an international cooperation as large as possible with at least three partners and remaining opened to the present  partners of the project and other potentially interested countries.

The agreement will include a comprehensive financial framework which allows ITER construction while preserving a vigorous accompanying programme of research and technological development in order to accelerate the development of the fusion energy.

The result of these negotiations will be presented at the next session of the Council, at (25 and 26 November 2004), to reach agreement on the main elements of the future international agreement on ITER.

Press Release (draf) Council of the European Union, Competitiveness (Internal Market, Industry and Research), 24/09/2004 (PDF) or WebSite of the European Council

Fusion Technology : Annuel Report of the Association Euratom-CEA. Juin 2003

Executive Summary (30p, pdf, 3 179 Ko)

Full report (385p, pdf, 36 771 Ko)

• Cover, contents, introduction (14p, pdf,1 683 Ko)
• Plasma integration (47p, pdf, 4 857 Ko)
• Plasma facing components (57p, pdf, 5 958ko)
• Vessel/In Vessel (37p, pdf, 4 223 Ko)
• Remote Handling (53p, pdf, 6 756 Ko)
• Magnets (37p, pdf, 2 960 ko)
• Breeding blankets (48p, pdf, 14 706 ko)
• Structural materials (91p, pdf, 8 104 ko)
• Safety (30p, pdf, 2 692ko)
• Reactor studies (56p, pdf, 4 630 ko)
• Appendix (32p, pdf, 1 958 ko)

European Union chose Cadarache as the European site to host ITER (see the press release from french ministry for Research and New Technologies  or PDF, ,  see the press release from UE Commission, ou PDF, ). 

The final selection between the Japanese site (Rokkasho-mura), the Canadian site (Clarington) and the European site (Cadarache) is foreseen before the end of December.

 Speech by the Prime Minister

Visiting Tore Supra

Rond table discussion with local politicians and representatives of the economic development structures

Visiting the  ITER site

In front of journalists of about fifteen different nationalities, Mrs Claudie Haigneré recalled engagements of the French government about the French candidature as well as the exceptional assets of the site of Cadarache

Claudie Haigneré expressed the full support of the French government for the French candidature during a speech to DRFC (Research Controlled Fusion Department) people.

Claudie Haigneré's speech (or pdf file)   

For further information :
www.iter.gouv.fr / Press release
www.itercad.org
ITER

Fusion Technology : Annuel Report of the Association Euratom-CEA. Juin 2002

• Cover, contents, introduction (13p, pdf,1576 ko)
• Plasma integration (30p, pdf, 5 827 ko)
• Plasma facing components (37p, pdf, 4387ko)
• Vessel/In Vessel (58p, pdf, 5 375 ko)
• Remote Handling (46p, pdf, 5 487 ko)
• Magnets (30p, pdf, 2 789 ko)
• Breeding blankets (78p, pdf, 5 965 ko)
• Structural materials (117p, pdf, 14 312 ko)
• Fuel cycle (14p, pdf, 896 ko)
• Safety (32p, pdf, 3 790ko)
• Reactor studies (56p, pdf, 4 630 ko)
• Inertial confinement (24p, pdf, 2 170 ko)
• Appendix (34p, pdf, 1 359 ko)

Claudie Haigneré expressed the full support of the French government for the French candidature during a speech to DRFC (Research Controlled Fusion Department) people.

Claudie Haigneré's speech (or pdf file)   

www.itercad.org

Web pages dedicated to Cadarache as european site for ITER are available : follow the link www.itercad.org .

Do not hesitate to consult them to discover the characteristics of Cadarache, its scientific and industrial background,...

For further information :
Cadarache as European site for ITER
ITER