SUMMARIZED RESULTS OF THE CRYOSORPTION PANEL TEST PROGRAMME FOR THE ITER CRYOPUMPING SYSTEM

A reliable but versatile primary cryopumping system is required for high vacuum pumping of the ITER to-rus during all phases of plasma operation. To achieve that goal, an extensive R&D programme has been perform-ed 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. 1