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Annual Report 2005 Annual Reportannual 2005 Max-Planck-Institut für Plasmaphysik Annual Report 2005 Annual ReportAnnual 2005 Max-Planck-Institut für Plasmaphysik Imprint Annual Report 2005 Max-Planck-Institut für Plasmaphysik (IPP) Boltzmannstraße 2 85748 Garching bei München phone (0 89) 32 99-01 View into the test chamber of the new ion beam facility GLADIS for the testing of plasma facing components. fax (0 89) 32 99-22 00 http://www.ipp.mpg.de In the central part of the picture, an actively cooled Wendelstein 7-X pre-series divertor target element is loaded with a H beam. The beam power density of 10 MW/m2 heats the CFC surface up to ~1000 °C during the test. Editorial Team Dr. Petra Nieckchen Andrea Henze Printing Druckerei Behr, Scheyern-Fernhag 2006 Copyright by IPP Printed in Germany ISSN 0179-9347 Further Information This work was performed under the terms of the agreement between Max-Planck- Institut für Plasmaphysik and the European Atomic Energy Community to conduct joint research in the field of plas- ma physics. All rights reserved. Reproduction – in whole or in part – sub- ject to prior written consent of IPP and inclusion of the names of IPP and the author. EURATOM Association Annual Report 2005 The Max-Planck-Institut für Plasmaphysik is an institute of the Max Planck Gesellschaft, part of the European Fusion Programme (Euratom) and an associate member of the Helmholtz-Gemeinschaft Deutscher Forschungszentren. The year 2005 represents an extremely impor- A technical highlight in 2005 was the success- tant milestone in the history of fusion: The EU ful commissioning of a new integrated control and its partners decided on 28th June to go and data acquisition system that is specially ahead with the ITER project and selected the adapted to ITER needs. This system is now in European site in Cadarache, France. It is routine use at ASDEX Upgrade. The coverage expected that the seven partners will initial the of the vessel interior with tungsten, which will ITER Implementing Agreement later this be crucial for future machines, was further spring. IPP is extensively involved in the extended in 2005. Complete coverage of tung- development of this important experiment, sten is the aim for the 2006 summer shut- which is universally accepted as the decisive down. The parameter range for improved H- “next step” in fusion research. mode operation has been extended to the Alexander M. Bradshaw ITER collisionality and beta values. This Changes in the organisation of the Wendelstein mode of tokamak operation, discovered at 7-X stellarator project took place in 2005: Prof. ASDEX Upgrade in 1999, now promises – Thomas Klinger became Co-Director; the other Co-Director, Dr. under nominal ITER operating conditions – either higher fusion Remmelt Haange, formerly at JET and until recently Head of the performance or, alternatively, longer pulses of up to one hour. In ITER Site in Naka, assumed his position – also as Technical view of ITER, efforts to study the behaviour of fast ions in ASDEX Director – in September. The Directorate and the Board of Upgrade have also been vigorously pursued. Using a new fast ion Scientific Directors have thanked Prof. Friedrich Wagner on sever- loss diagnostics, it has been possible for the first time to identify al occasions for his dedicated and unstinting contribution to the directly the phase correlation of fast ions losses with MHD activity construction of this experiment, which is so important for IPP and such as neo-classical tearing modes or ELMs. for the fusion community as a whole. There was considerable progress on construction in 2005, but the project still struggles The past year for JET was marked by a series of technical difficul- with assuring the punctual delivery of components of the required ties, which have prevented several key experiments from being car- high quality from the many hundred suppliers. The highly complex ried out. The major project of the last shutdown, namely the ITER- vacuum vessel – a milestone in welding technology – was complet- like antenna, could not be installed. A major highlight is the ed and delivered to Greifswald. Also, the first two segments of the approval of a further enhancement programme involving invest- massive central support ring are now undergoing final machining ments of ca. 50 MEuro. The main elements are the installation of and will be delivered shortly. Most of the contracts for manufactur- an ITER-like wall and an upgrade of the neutral beam heating ing and delivery of components are running smoothly from the power. IPP is involved in the preparation of the coming campaigns technical point of view. Most importantly, the assembly of the first as well as in some enhancement projects, notably the development half-module began on 6th April. Meanwhile, coils of the various of tungsten coatings for the ITER-like wall. types are being delivered in Greifswald and prepared for assembly. Staff numbers are being increased further, almost exclusively on Plasma-wall interaction studies and materials research have led to the engineering side. The substantially improved manpower situa- major advances in the understanding of the hydrogen retention tion and the growing in-house expertise have now put the project processes in tungsten and carbon materials. For ITER the very into a position to cope more efficiently with the day-to-day issues important question of the hydrogen behaviour in mixed materials is of contract supervision, quality assurance, change management, now being addressed in a special programme. The European Task test and design, structural analysis and other areas. The network of Force on Plasma-Wall Interactions will now led by Dr. Roth of IPP international collaborations on Wendelstein 7-X diagnostics devel- for of the next three years, indicating the significance of IPP work opment has been extended, with special emphasis on new EU in the European context. member states. In a similar connotation IPP continues to coordinate the EU The programme on the ASDEX Upgrade tokamak, conducted in Integrated Project “ExtreMat” in which 37 European partner insti- close collaboration with our EU partners, continues to address tutions have joined to develop materials for extreme environments. physics questions that have an immediate impact on the ITER In this project one key application for such newly developed mate- design. Moreover, it plays an important role in establishing the rials is of course fusion energy. physics base for ITER operation in both the standard scenario as well as in scenarios with improved performance. Moreover, physics Again this year, the Directorate and the Board of Scientific issues with impact beyond ITER, i.e. for future power plants such as Directors note with pride the outstanding scientific results obtained DEMO, have already been identified and are being addressed. This in the Divisions as well as the high level of dedication of the IPP is accompanied by the development of the relevant technologies in staff. Their success will ensure that IPP will continue to play a piv- diagnostics, heating and current drive, but also control systems. otal role in fusion research in the years to come. III Content Tokamak Research University Contributions to IPP Programme ASDEX Upgrade . .3 Cooperation with Universities . .99 JET Cooperation . .29 University of Augsburg Lehrstuhl für Experimentelle Plasmaphysik . .101 Stellarator Research University of Bayreuth Lehrstuhl für Experimentalphysik III . .103 Wendelstein 7-X . .33 University of Berlin Wendelstein 7-X Applied Theory . .55 Lehrstuhl für Plasmaphysik . .105 Laboratory Plasma Devices WEGA and VINETA . .59 Technical University of Munich Speckle metrology for surface diagnostics . .107 ITER University of Stuttgart Institut für Plasmaforschung (IPF) . .109 ITER Cooperation Project . .63 Publications Fusion Technology Publications and Conference Reports . .113 Plasma-facing Materials and Components . .69 Lectures . .149 Energy and System Studies . .75 Laboratory Reports . .171 Electron Spectroscopy . .77 Teams . .173 Plasma Theory Appendix Theoretical Plasma Physics . .81 How to reach IPP in Garching . .176 How to reach Greifswald Branch Institute of IPP . .177 Infrastructure Organisational structure of Max-Planck-Institut für Plasmaphysik . .178 Computer Center Garching . .93 V Tokamak Research ASDEX Upgrade Head: Dr. Otto Gruber 1 Overview The main aim of the ASDEX Upgrade pro- tions to IPP programme) and gramme is to prepare the physics base of ITER international collaborations 1.1 Scientific aims and operation and DEMO. Significant progress has been made (see section 10). The tokamak fusion experiment in the operation with tungsten-clad walls, under- The AUG Programme Committee ASDEX Upgrade (AUG) went standing of transport and impurity control, ELM established in 2001 enables the into operation in 1991 after mitigation by frequency control, and control of Associations to take responsi- nearly 10 years of planning, de- performance limiting instabilities. The improved bility for our programme. This sign and construction. The AUG H-mode operation was extended into ITER body defines the Task Forces design combines the successful parameter ranges and beyond the ITER baseline responsible for the different ele- divertor concept with the re- specifications for nTτ and the pulse length. ments of our programme, nomi- quirements of a next step fusion nates the Task Force Leaders reactor, in particular the need and approves the experimental for an elongated plasma shape and poloidal magnetic field programme. Furthermore, the bodies that work out the pro- coils outside the toroidal magnetic field coils. AUG is close gramme proposals are open to external participants, and to ITER in its magnetic and divertor geometry and in particu- remote participation in the meetings is used. For the 2005 lar the relative length of both divertor legs compared to the campaign 153 proposals were received including 49 propo- plasma dimensions. The installed heating power of up to sals from outside IPP. With this structure, we have achieved 28 MW ensures that the energy fluxes through the plasma a compromise between the increased international participa- boundary are equivalent to those in ITER.
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