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This is the annual report of the Association FZK-EURATOM which contributes to various fields of the European Next Step Fusion Technology Programme. The work is strongly focused on the ITER engineering design activity. Development of superconducting magnets and microwave heating systems are equally important for the stellarator programme Wendelstein 7X. FZK has upgraded the TOSKA magnet test facility to be able to test, successively, the prototype coil for W7X and the ITER toroidal field model coil. Major modifications are being made to the power supplies and the fast switching system in view of high current (80 kA), fast discharge operation of the ITER model coil. Advances have been made in the field of vacuum technology and fuel cycle. Activities have been ongoing for ITER contributing to the field of plasma facing components. They cover three different aspects of first wall behaviour under the impact of the plasma: tritium uptake, plasma erosion and cyclic heat load.

Additional information

Authors: KAST G (EDITOR), Forschungszentrum Karlsruhe GmbH (DE)
Bibliographic Reference: EUR 18156 EN (1997) 139pp., FS
Availability: Available from Forschungszentrum Karlsruhe, Postfach 3640, D-76021 Karlsruhe (DE)
ISBN: ISSN 0947-8620
Record Number: 199810223 / Last updated on: 1998-03-09
Original language: en
Available languages: en
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