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C. Day1, H. Haas1,
N. T. Kazakovsky2, A. Mack1,
D. K. Murdoch3, D. Röhrig4,
G. L. Saksagansky5
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.
IAEA 2001
