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Streibl, B.; Mukherjee, S.
Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.)1989
Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.)1989
AbstractAbstract
[en] This is a summary of the TF-magnet calculation results for the 1984 phase-II proposal including supplements (also considering disturbances) of the performance of ASDEX Upgrade. Calculation results are as reliable as the assumptions incorporated, so that investigations of materials and design components were always used to complete the calculations. (orig.)
[de]
Die Ergebnisse der Berechnungen fuer den TF-Magneten wurden erstmals fuer den 1984 erfolgten Phase-II-Antrag zusammengefasst. Mittlerweile gibt es Ergaenzungen, die verstreut in Veroeffentlichungen, Ringbuchblaettern und Berichten von Herrn Mukherjee vorliegen. Sie sollen hier zusammenfassend, unter Beruecksichtigung von Stoerfaellen, fuer den Betrieb von ASDEX Upgrade interpretiert werden. Rechenergebnisse sind nur so verlaesslich wie die Annahmen, die in sie eingehen. Material- und Bauteiluntersuchungen ergaenzten daher die Berechnungen von Anfang an. Sie wurden im Wesentlichen von den Firmen IABG und MAN-T durchgefuehrt. Der Bericht geht nicht auf Details der Versuche ein. Es wird vielmehr versucht, wieder verwertbare Ergebnisse herauszuschaelen. (orig.)Original Title
Erwartete Betriebseigenschaften des ASDEX Upgrade Toroidalfeld Magneten aufgrund von Berechnungen und Materialuntersuchungen
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Nov 1989; 35 p
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AbstractAbstract
No abstract available
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Anon; p. 31; 1976; 9. symposium on fusion technology; Garmisch-Partenkirchen, F.R. Germany; 14 Jun 1976; AED-CONF--76-309-030; Short communication only. Available from ZAED.
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No abstract available
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CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Dept. de la Physique du Plasma et de la Fusion Controlee; Commission of the European Communities, Luxembourg. Center for Information and Documentation; p. 333-344; Dec 1972; 7th symposium on fusion technology; Grenoble, France; 24 Oct 1972; 4 figs.
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AbstractAbstract
[en] The geometric arrangement of 20 discrete quadrupole magnets producing a magnetic field similar to that of the well-known helical l=2 stellarator windings is described. The magnetic forces in a single magnet and the mechanical stresses on the coil housing are analysed. The magnetic properties of the 20-magnet arrangement are shown for m=2, 3, 4, 5 toroidal field periods. The m=4 configuration is treated in more detail and compared with an equivalent hedical winding
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Commission of the European Communities, Brussels (Belgium); p. 217-223; ISBN 0 08 021369 3; ; 1976; p. 217-223; 9. Symposium on fusion technology; Garmisch-Partenkirchen, Germany, F.R; 14 - 18 Jun 1976; Published by Pergamon Press
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Brossmann, U.; Gruber, J.E.; Haubenberger, W.D.; Jandl, O.; Soell, M.; Streibl, B.
Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.)1979
Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.)1979
AbstractAbstract
[en] The report comprises three sections. Section A presents the essential features of the present design of a tape-wound magnet with respect to the magnetic, thermal and radiological loads resulting from the physical assumptions for the ZEPHYR experiment. The conceptual requirements for the liquid-nitrogen cooling of the magnet are given and concepts under discussion are presented. To allow a first pronouncement on the mechanical load capacity of critical magnet components, the results available from calculations and experiments relating to the conductor and insulation materials are interpreted. As investigation of the material properties must play an important role in consolidating the magnet concept, special sections of the report are devoted to this subject. Section B deals theoretically with the conductor material problem, reviews the available experimental results, both with respect to material properties and technical production, and takes a look ahead at future activities. The insulation material is treated on similar lines in Section C. (orig.) 891 HT/orig. 892 HIS
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Nov 1979; 191 p; With figs. and tabs.
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AbstractAbstract
No abstract available
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Ceskoslovenska Akademie Ved, Prague. Ustav Fyziky Plazmatu; p. 25-30; nd; p. 25-30; 8. European conference on controlled fusion and plasma physics. Stellarator workshop; Zdikov, Czechoslovakia; 26 - 28 Sep 1977; Published in summary form only.
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Sihler, C.; Huart, M.; Kaesemann, C.-P.; Streibl, B., E-mail: sihler@ipp.mpg.de
arXiv e-print [ PDF ]2003
arXiv e-print [ PDF ]2003
AbstractAbstract
[en] The power and energy of the ASDEX Upgrade (AUG) tokamak are provided by two separate 10.5 kV, 110-85 Hz networks based on the flywheel generators EZ3-EZ4 in addition to the generator EZ2 dedicated to the toroidal field coil. The 10.5 kV networks supply the thyristor converters allowing fast control of the DC currents in the AUG poloidal field coils. Two methods for improving the load power factor in the present experimental campaign of AUG have been investigated, namely the control of the phase-to-neutral voltage in thyristor converters fitted with neutral thyristors, such as the new 145 MVA modular thyristor converter system (Group 6), and reactive power control achieved by means of static VAr compensators (SVC). The paper shows that reliable compensation up to 90 MVAr was regularly achieved and that electrical transients in SVC modules can be kept at an acceptable level. The paper will discuss the results from the reactive power reduction by SVC and neutral thyristor control and draw a comparative conclusion
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22. symposium on fusion technology; Helsinki (Finland); 9-13 Sep 2002; S0920379603002874; Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Duesing, G.; Freudenberger, K.; Kolos, J.; Streibl, B.; Wulff, G.
Sixth symposium on engineering problems of fusion research1976
Sixth symposium on engineering problems of fusion research1976
AbstractAbstract
[en] The design of the toroidal vacuum vessel and the helical winding of the Wendelstein VII B stellarator has been completed. The electromagnetic forces acting on the winding have called for a support structure assembled from a thick-walled torus upon which the conductors are wound and forty structure groups around this. The rigid compound structure limits the critical stresses in the helical conductors and at the junction of the torus and its removable segment. Thermal stresses arising in the conductors and the torus wall are limited by water-cooling. The complex manufacturing procedure requires expertise in many different techniques
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Anon; p. 768-772; 1976; p. 768-772; Institute of Electrical and Electronics Engineers, Inc; New York; 6. IEEE symposium on engineering problems of fusion research; San Diego, CA, USA; 17 - 21 Nov 1975
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Sihler, C.; Huart, M.; Stobbe, F.; Streibl, B.; Treutterer, W.; Joswig, A., E-mail: sihler@ipp.mpg.de
arXiv e-print [ PDF ]2003
arXiv e-print [ PDF ]2003
AbstractAbstract
[en] The ASDEX Upgrade (AUG) tokamak requires an electrical power up to a few hundred MVA for a time period of 10-20 s. The power and energy is provided by three separate networks based on flywheel generators. In 1999, during a routine check performed on generator EZ3, it was discovered that coupling bolts of the flywheel generator shaft were deformed. Given that the active load of the generator (∼100 MW) in service is well below the design value of the shaft (∼800 MW), the damages may only be explained by a torsional resonance of the shaft line, itself excited by active power transients from the converter loads. A value of 23.6 Hz was calculated for the first eigen-frequency of the shaft line. Frequencies between 10 and 30 Hz have been identified in the spectrum of the load curves. Since torsional shaft oscillations are characterised by very low damping, torsional resonance can become dangerous even for over-dimensioned generator shafts. Therefore, a novel 'torque' measurement system was installed. The paper presents results from calculations and measurements showing that devices capable to measure the stress in the shaft line are essential for generator protection in feedback controlled fusion experiments
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22. symposium on fusion technology; Helsinki (Finland); 9-13 Sep 2002; S0920379603002758; Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Jandl, O.; Kollotzek, H.; Springmann, E.; Streibl, B.
Fusion technology 1982. Proceedings of the 12. symposium held in Juelich, 13-17 September 1982. 2 v1983
Fusion technology 1982. Proceedings of the 12. symposium held in Juelich, 13-17 September 1982. 2 v1983
AbstractAbstract
[en] ASDEX Upgrade (UG), a divertor tokamak with a minor plasma radius of a = 0.5 m and a plasma current of 1.2 to 1.5 MA, is intended to succeed ASDEX. A major target of this experiment is to investigate a reactor-compatible plasma boundary. This requires according to a toroidal field (B0) at the plasma centre normalized to the aspect ratio (A) of B0/A approximately = 1.2. The optimum with due allowance for physical requirements and technical constraints of the complete tokamak system was obtained in this case for B0 = 3.9 T (A = 3.25) and a plasma radius of 1.63 m. The toroidal field (TF) magnet designed to meet these requirements is presented. Aspects of its turnover structure such as force transfer, coil housing and access to the plasma vessel are described. The coil concept developed in collaboration with industry is also presented, in particular the conductor concept and the current terminals and water manifold designs. Finally, the results of the cooling and stress analysis are summarized. (author)
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Association Euratom-Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.); 1532 p; ISBN 0 08 029977 6; ; 1983; v. 2 p. 1039-1044; Pergamon Press; Oxford (UK); Fusion technology 1982; Juelich (Germany, F.R.); 13-17 Sep 1982
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