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Book of Invited Abstracts 24th Symposium on Fusion Technology 11 - 15 September 2006 - Palace of Culture and Science, Warsaw, Poland BOOK OF INVITED ABSTRACTS How to read Paper Identification Code (SN-T-I): S = Session (PL=Plenary, P=Poster, O=Oral) N = Session number (parallel sessions numbered 1A, 1B etc.) T = TOPIC (i.e. "I" = Materials Technology) I = ID number Table of Contents (PL1-O-574) Norbert Holtkamp; An Overview of the ITER Project 1 (PL1-O-551) Jerome Pamela et al.; THE CONTRIBUTION OF JET TO ITER 2 (PL1-O-550) Shinzaburo Matsuda; The EU/JA Broader Approach Activities 3 (PL2-O-561) Felix Schauer; Status of Wendelstein 7-X Construction 4 (PL2-O-554) Mark Henderson; EU Developments of the ITER ECRH System 5 (PL2-O-146) Songtao Wu; An Overview of the EAST Project 6 (PL3-O-564) Vanni Antoni; The ITER Neutral Beam system: status of the project and review of the main technological issues 7 (PL3-O-560) Manfred Glugla et al.; THE ITER TRITIUM SYSTEMS 8 (PL3-O-552) Daniel Ciazynski; Review of Nb3Sn conductors for ITER 9 (PL4-O-571) Maurizio Gasparotto; European technology activities to prepare for ITER component procurement 10 (PL4-O-303) Jean-Philippe GIRARD et al.; ITER Safety and Licensing 11 (PL5-O-553) Rainer Laesser et al.; Development, simulation and testing of structural materials for DEMO 12 (PL5-O-545) Michael Kaufmann; Tungsten as First Wall Material in Fusion Devices 13 (PL5-O-549) David Ward; The Contribution of Fusion to Sustainable Development 14 (PL5-O-563) Karl Lackner; Technology and Plasma Physics Developments needed for DEMO 15 24th Symposium on Fusion Technology 11 - 15 September 2006 - Palace of Culture and Science, Warsaw, Poland Invited presentations An Overview of the ITER Project (PL1-O-574) Norbert Holtkamp Cadarache Joint Work Site Building 507 13108 St Paul lez Durance France With the choice of the ITER construction site at Cadarache in June 2005, and the gradual selection of the ITER Project Team who will supervise the construction, the Project is now in a phase of ever heightening activity, increasingly focussed on the immediate needs of implementation, and increasingly attracting and stimulating the interest of the general public. The new organisation is currently being shaped, and the recruitment process has begun for the most senior members of the future ITER Staff. This allows technical preparations for construction to continue smoothly until the ITER Organisation can be set up. The greatest efforts are being made, both in the transition plans and in the new organisation, to preserve the legacy of technical knowhow built up in the central team since 1992. The new organisation is particularly strong initially in the most urgent areas, related to long lead items - magnets, the main vessel and the buildings - as well as in work related to licensing. But the team also incorporates new functional needs - financial, administrative, and procurement - and moves to tie in better the needs of future users in the diagnostic, heating, and test blanket development areas. Over the last two years, internal systems have also been built up, and project control procedures gradually tightened, with a view to satisfying licensing requirements and assuring the highest quality device. Since the bulk of the procurement for ITER will be provided in kind by the ITER Parties, efforts have been strengthened to define better the future links to and responsibilities of the Domestic Agencies. The agreed sharing of the procurement at the negotiation level has needed to be transferred into realistic technical splitting of the work, and this process is still underway. Also the procedures have been established which are to be followed in order to minimise the risk to the Parties of project time or cost overruns. The design of course has evolved in its details along with the surrounding technical context since originally conceived and valued five years ago. Design reviews of specific procurements have therefore been or are to be made to ensure the current manufacturing and design assumptions continue to satisfy the requirements. Regarding licensing, considerable effort is being made to tailor the documentation and underlying analyses to satisfy the norms the French licensing authority is familiar with, and to anticipate the requirements for a speedy licensing process. A public debate process has also been passed successfully. This paper will review the current status of development of the ITER Project, covering both organisational and technical issues. 1 24th Symposium on Fusion Technology 11 - 15 September 2006 - Palace of Culture and Science, Warsaw, Poland Invited presentations THE CONTRIBUTION OF JET TO ITER (PL1-O-551) Jerome Pamela(1), M. L. Watkins(2), A. Lioure(2), G. Matthews(3), V. Philipps(4), C. Grisolia(5), T. Jones(3), M. Nightingale(3), F. Durodié(6), A. Murari(7), A. Géraud(8) 1. EFDA-Close Support Unit, Culham Science Centre Abingdon UK 2. EFDA-JET, Culham Science Centre Oxfordshire OX14 3EA Abingdon UK 3. EURATOM/UKAEA Fusion Association Culham Science Centre OX143DB Abingdon United Kingdom 4. Forschungszentrum Jülich GmbH, EURATOM-Association D-52425 Jülich 52425 Jülich Germany 5. Association Euratom-CEA, CEA/DSM/DRFC CEA-Cadarache 13108 ST PAUL-LEZ-DURANCE France 6. Association EURATOM-Belgian State, Ecole Royaly Militaire Avenue de la Renaissance 30 B-1000 Brussel BELGIUM 7. Associazione EURATOM- ENEA sulla Fusione, Via Enrico Fermi 45, I-00044 Frascati (RM), Italy 8. Association Euratom CEA, CEA/DSM/DRFC Cadarache 13108 St Paul Lez Durance France The mid-term JET experimental programme will exploit the recently enhanced scientific capabilities of the JET tokamak. The divertor has been modified allowing high triangularity ITER relevant scenarios to be run at high plasma current; sixteen new or upgraded diagnostics are being made operational and a new ITER-like Ion Cyclotron Resonant Heating (ICRH) antenna will be installed for operation in 2007. The experimental campaigns will be devoted to studying critical issues potentially impacting the detailed design of ITER components (e.g. first wall, heating and current drive systems, diagnostic) and, in parallel, aiming at further developing ITER operating scenarios and address specific physics issues of direct relevance to ITER (e.g. transport physics, burning plasma physics). For the longer term, work on a “JET programme in support of ITER” has begun, which aims at making optimal use of JET’s unique features: large plasma size and capability to handle beryllium (Be) and tritium (T). ITER is currently designed to have a beryllium-clad first wall, tungsten (W) brushes at the divertor entrance and carbon fibre reinforced carbon (CFC) tiles at the divertor strike points. This combination of materials has never been tested in a tokamak. The ITER-like wall project on JET, planned for installation starting mid 2008, will use a combination of Be on the first wall, bulk-W and W-coated CFC tiles in the divertor. W-coating and bulk W technologies have been selected as result of one year of intensive R&D. The experimental programme will include T-retention studies, material erosion and migration, mixed materials effects, melt layer behaviour and impurity control, and operational scenario compatibility with a Be/W material mix. Techniques for avoiding the issues caused by the effects of expected large Edge Localised Modes (ELMs) on the walls and divertor in ITER will be tested in JET with the installation of a pellet injector with a high repetition rate (up to 50 Hz), for ELM pace making as demonstrated on ASDEX Upgrade. In order to increase the ITER-relevance of the plasma scenarios, additional neutral beam heating power, up to 36 MW for 20s (compared to 25 MW for 10s presently) will be provided by upgrading the existing beam boxes and power supplies for operation at higher current. Phasing the two beam boxes will make it possible to deliver 17-18 MW of neutral beam power for up to 40s, for full exploitation of the pulse length capability of the JET machine. This will be essential ingredient to progress, in particular, hybrid and advanced scenarios for ITER, which require full or partial current profile control. Finally, diagnostics required to support further developments of ITER plasma scenarios, as well as ITER diagnostics that need to be tested on JET, such as fast wave reflectometer and radiation hard hall probe, will be implemented mostly by upgrading existing systems. Besides tokamak experiments, the JET activities in support of ITER include also technology R&D. A particular focus has been put recently on activities aiming at characterising dust and erosion/deposition areas in JET, improving in-situ T removal techniques and providing support in topics relevant to the licensing of ITER. 2 24th Symposium on Fusion Technology 11 - 15 September 2006 - Palace of Culture and Science, Warsaw, Poland Invited presentations The EU/JA Broader Approach Activities (PL1-O-550) Shinzaburo Matsuda Japan Atomic Energy Agency Sumitomo Fudosan Ueno blg. No8, 7F 110-0015 Higashiueno 6-9-3, Taito-ku, Tokyo Japan At the time of ITER site decision in Moscow on 28 June 2005, representatives of EU and Japan jointly declared their intention to implement Broader Approach Activities in support of ITER on a time frame compatible with its construction phase. On the basis of this declaration, working groups from the Parties were established to identify possible key areas of joint activities. As a result of intense discussions, agreement has been reached by both Parties as follows. The Broader Approach Activities comprise the following three projects: 1) Engineering Validation and Engineering Design Activities for the International Fusion Materials Irradiation Facility (IFMIF/EVEDA) 2) the International Fusion Energy Research Center (IFERC), comprising: a)A DEMO Design, R&D coordination Center aiming at establishing a common basis for a DEMO design, b)A Computational Simulation Center composed of super-computer facilities for large scale simulation activities, and c)An ITER Remote Experimentation Center to facilitate broad participation of scientists into ITER experiments.
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