Community Research and Development Information Service - CORDIS

Abstract

The CEA Association is involved, in close collaboration with ENEA, FZK, IPP and UKEA European Associations, in the firat ITER neutral beam injector and the ITER neutral beam test facility design (EFDA task ref. TW3-THHN-IITF1). A total power of about 50 MW will have to be removed in steady state on the neutral beam test facility (NBTF). The main purpose of this task is to make progress with the detailed design of the first ITER NB injector and to start the conceptual design of the ITER NBTF.
The general infrastructure layout of a generic site for the NBTF, includes the test facility itself equipped of a dedicated beamline vessel and integration studies of associated auxiliaries as cooling plant, cryoplant and fore pumping system. The general infrastructure and auxiliaries layout of the NBTF are described.

Additional information

Authors: CORDIER J J (Editor), Departement de Recherches sur la Fusion Controlee, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR)
Bibliographic Reference: An oral paper given at: 23rd Symposium on Fusion Technology Organised by: Consorzio RFX Held at: Fondazione Cini, Venice, Italy
Availability: Available from Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail: dirdrfc@drfc.cad.cea.fr
Record Number: 200417714 / Last updated on: 2004-10-14
Category: PUBLICATION
Original language: en
Available languages: en