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(ITERP2/07) Summarized Results of the Cryosorption Panel Test Programme for the ITER Cryopumping System

   
C. Day 1, H. Haas 1, N. T. Kazakovsky 2, A. Mack 1, D. K. Murdoch 3, D. Röhrig 4, G. L. Saksagansky 5
 
1 Forschungszentrum Karlsruhe, Hauptabteilung Ingenieurtechnik, PO Box 3640, 76021 Karlsruhe, Germany
2 RFNC-All-Russian Research Inst. of Experimental Physics (VNIIEF), Sarov, Russia
3 NET Team, Max-Planck Inst. für Plasmaphysik, Garching, Germany
4 Forschungszentrum Karlsruhe, Projekt Kernfusion, Karlsruhe, Germany
5 D.V. Efremov Scientific Research Inst. of Electrophysical Apparatus (NIIEFA), St. Petersburg, Russia

Abstract
A reliable but versatile primary cryopumping system is required for high vacuum pumping of the ITER  torus during all phases of plasma operation. To achieve that goal, an extensive R&D programme has been performed within the framework of the Nuclear Fusion Project of FZK, supported by the European Communities under the European Fusion Technology Programme. The present paper covers that part of the programme, which focuses on the pumping speed of the recommended cryopanel type and the various aspects of the charcoal-bonding system  in the cryogenic temperature range. It is demonstrated that the investigated cryosorption panels exhibit a very good behaviour with respect to pumping efficiency, long-term thermomechanical endurance and compatibility with tritium. The recommended cryopump design was therefore chosen as point design for ITER.

 

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IAEA 1999