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Title: Gyrotron Development in the EU for Present Fusion Experiments and for ITER

Abstract

The long term strategy of the EU in the field of gyrotrons in fusion plasma applications is based on two approaches: R and D in laboratories to develop advanced concepts and industrial development of state-of-the-art tubes for use in present experiments like TCV, Tore Supra (118 GHz, 0.5 MW, CW) and W7-X (140 GHz, 1 MW, CW). The results from these two approaches are then applied to the development of a coaxial cavity gyrotron operating at 170 GHz and delivering 2 MW-CW for the electron cyclotron wave system of ITER. This paper will recall the main achievements of this program and will outline the present status of the 170 GHz coaxial cavity gyrotron development.

Authors:
 [1];  [2]; ; ; ;  [3];  [4]; ; ;  [5]; ; ; ; ; ; ;  [1]; ;  [6];  [7] more »;  [8] « less
  1. Forschungszentrum Karlsruhe, Association EURATOM-FZK, IHM, Postfach 3640, D-76021 Karlsruhe (Germany)
  2. (Germany)
  3. Centre de Recherches en Physique des Plasmas, Association EURATOM -- Confederation Suisse, EPFL Ecublens, CH-1015 Lausanne (Switzerland)
  4. Universitaet Karlsruhe, IHE, Kaiserstr. 12, D-76128 Karlsruhe (Germany)
  5. Thales Electron Devices, 2 Rue Latecoere, F-78141 Velizy-Villacoublay (France)
  6. Association EURATOM - CEA, CEA/DSM/DRFC, Centre de Cadarache, 13108 Saint-Paul-lez-Durance (France)
  7. Helsinki University of Technology, Association EURATOM - TEKES, FIN-02150 Espoo (Finland)
  8. Institut fuer Plasmaforschung, Universitaet Stuttgart, Paffenwaldring 31, D-70569 Stuttgart (Germany) (and others)
Publication Date:
OSTI Identifier:
20787666
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 807; Journal Issue: 1; Conference: 7. workshop on high energy density and high power RF, Kalamata (Greece), 13-17 Jun 2005; Other Information: DOI: 10.1063/1.2158772; (c) 2005 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CAVITY RESONATORS; ECR HEATING; ELECTRONS; GHZ RANGE; ITER TOKAMAK; MICROWAVE AMPLIFIERS; PLASMA; RF SYSTEMS; TCV TOKAMAK; TORE SUPRA TOKAMAK

Citation Formats

Thumm, M., Universitaet Karlsruhe, IHE, Kaiserstr. 12, D-76128 Karlsruhe, Alberti, S., Hogge, J.-P., Tran, M. Q., Yovchev, I., Arnold, A., Bariou, D., Giguet, E., Lievin, C., Dammertz, G., Illy, S., Jin, J., Piosczyk, B., Prinz, O., Rzesnicki, T., Yang, X., Darbos, C., Magne, R., Dumbrajs, O., and Gantenbein, G. Gyrotron Development in the EU for Present Fusion Experiments and for ITER. United States: N. p., 2006. Web. doi:10.1063/1.2158772.
Thumm, M., Universitaet Karlsruhe, IHE, Kaiserstr. 12, D-76128 Karlsruhe, Alberti, S., Hogge, J.-P., Tran, M. Q., Yovchev, I., Arnold, A., Bariou, D., Giguet, E., Lievin, C., Dammertz, G., Illy, S., Jin, J., Piosczyk, B., Prinz, O., Rzesnicki, T., Yang, X., Darbos, C., Magne, R., Dumbrajs, O., & Gantenbein, G. Gyrotron Development in the EU for Present Fusion Experiments and for ITER. United States. doi:10.1063/1.2158772.
Thumm, M., Universitaet Karlsruhe, IHE, Kaiserstr. 12, D-76128 Karlsruhe, Alberti, S., Hogge, J.-P., Tran, M. Q., Yovchev, I., Arnold, A., Bariou, D., Giguet, E., Lievin, C., Dammertz, G., Illy, S., Jin, J., Piosczyk, B., Prinz, O., Rzesnicki, T., Yang, X., Darbos, C., Magne, R., Dumbrajs, O., and Gantenbein, G. Tue . "Gyrotron Development in the EU for Present Fusion Experiments and for ITER". United States. doi:10.1063/1.2158772.
@article{osti_20787666,
title = {Gyrotron Development in the EU for Present Fusion Experiments and for ITER},
author = {Thumm, M. and Universitaet Karlsruhe, IHE, Kaiserstr. 12, D-76128 Karlsruhe and Alberti, S. and Hogge, J.-P. and Tran, M. Q. and Yovchev, I. and Arnold, A. and Bariou, D. and Giguet, E. and Lievin, C. and Dammertz, G. and Illy, S. and Jin, J. and Piosczyk, B. and Prinz, O. and Rzesnicki, T. and Yang, X. and Darbos, C. and Magne, R. and Dumbrajs, O. and Gantenbein, G.},
abstractNote = {The long term strategy of the EU in the field of gyrotrons in fusion plasma applications is based on two approaches: R and D in laboratories to develop advanced concepts and industrial development of state-of-the-art tubes for use in present experiments like TCV, Tore Supra (118 GHz, 0.5 MW, CW) and W7-X (140 GHz, 1 MW, CW). The results from these two approaches are then applied to the development of a coaxial cavity gyrotron operating at 170 GHz and delivering 2 MW-CW for the electron cyclotron wave system of ITER. This paper will recall the main achievements of this program and will outline the present status of the 170 GHz coaxial cavity gyrotron development.},
doi = {10.1063/1.2158772},
journal = {AIP Conference Proceedings},
number = 1,
volume = 807,
place = {United States},
year = {Tue Jan 03 00:00:00 EST 2006},
month = {Tue Jan 03 00:00:00 EST 2006}
}
  • The gyrotron system for ECH and burn control on ITER requires at least 50 MW of RF power at frequencies near 170GHz operating in CW. To meet these requirements, high efficiency gyrotron tubes with {ge}1MW power output capability are necessary, as well as simple coupling to either a quasi-optical or waveguide transmission line. The paper reports the feasibility study on the design of an ITER-relevant gyrotron oscillator at 170GHz, 1MW CW employing a diode electron gun, an advanced internal quasi-optical converter, a cryogenically cooled single disk sapphire window, and a depressed potential collector. The operating mode selection and the cavitymore » design is a compromise between many design constraints.« less
  • The European Participant Team (PT) of the ITER project has developed coherent designs, validated in a comprehensive R and D programme, of the main systems which form the inner loop of the ITER Fuel Cycle (FC), consisting of the cryopumps (CP), mechanical backing pumps (RP), Torus Exhaust Processing (TEP), Isotope Separation System (ISS), Storage and Delivery System (SDS), and the Analytical System (ANS). The key objectives of the designs are flexibility to accommodate the different machine operating modes and parameter variations expected, minimization of global tritium inventory, and the use of robust, simple processing concepts to ensure longevity and easemore » of operation. The configuration of each of the systems has been frozen as a basis for a full investigation of the process performance, while the detailed mechanical and electrical design will be completed after site selection, as this may influence some details of the component selection and layout.« less
  • For many years the fusion community provided the main incentive for the development of internal-tin Nb3Sn. Several tonnes of moderate current density conductor with low AC losses were supplied for the U.S. Section of ITER CSMC. When the US abandoned the ITER project in 1998, the manufacturers began to concentrate on higher current density conductors for High Energy Physics. While there are significant differences between the strands for these two different applications, development in both areas has sufficient work in common to be of benefit to both communities. As the US reconsiders its position on ITER, the paper reviews somemore » of the past work and the present state of development in both fields.« less
  • Availability of D-T fusion neutrons at TFTR has offered an opportunity to conduct measurements of both short-lived and long-lived radioactivity of direct interest to ITER and DEMO reactors in a realistic tokamak fusion reactor environment. Materials irradiated, spatial locations, and certain features of activation characteristics at TFTR are described. 6 refs., 6 figs., 3 tabs.