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Abstract

The ITER neutral beam test facility (NBTF) is planned to be built, after the approval of the ITER construction and the choice of the ITER site, with the agreement of the ITER international team and of the JA and RF participant teams. The key purpose is to progressively increase the performance of the first ITER injector and to demonstrate its reliability at the maximum operation parameters: power delivered to the plasma 16.5 MW, beam energy 1 MeV, accelerated D{-} ion current 40 A, pulse length 3600 s.
Several interventions for possible modifications and for maintenance are expected during the early operation of the ITER injector in order to optimise the beam generation, aiming and steering. The maintenance scheme and the related design solutions are therefore a very important aspect to be considered for the NBTF design.
The paper describes consistently the many interrelated aspects of the design, such as the optimisation of the vessel and cryopump geometry, in order to get a better maintenance flexibility, an easier man access and a larger access for diagnostic and monitoring.

Additional information

Authors: ZACCARIA P, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);DAL BELLO S, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);MARCUZZI D, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);MASIELLO A, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);CONIGLIO A, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);ANTONI V, Consorzio RFX, Association EURATOM-ENEA, Padova (IT);CORDIER J J, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);HEMSWORTH R, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);ANTIPENKOV A, Forschungszentrum Karlsruhe, Institut für Technische Physik, Karlsruhe (DE);DAY C, Forschungszentrum Karlsruhe, Institut für Technische Physik, Karlsruhe (DE);DREMEL M, Forschungszentrum Karlsruhe, Institut für Technische Physik, Karlsruhe (DE);MACK A, Forschungszentrum Karlsruhe, Institut für Technische Physik, Karlsruhe (DE);PILLON M, ENEA, Centro Ricerche Frascati, Rome (IT);SANDRI S, ENEA, Centro Ricerche Frascati, Rome (IT);SPETH E, IPP CSU�Max-Planck-Institut für Plasma Physik, Garching (DE);TANGA A, IPP CSU�Max-Planck-Institut für Plasma Physik, Garching (DE);JONES T, UKAEA Culham EURATOM/UKAEA Fusion Association Culham Science Centre, Abingdon (UK);DI PIETRO E, EFDA CSU, Garching (DE);MONDINO P L, EFDA CSU, Garching (DE)
Bibliographic Reference: An article published in: Fusion Engineering and Design (2005), Volume 74, Issues 1-4, Pages 255-259
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://www.sciencedirect.com/science/journal/09203796
Record Number: 200719018 / Last updated on: 2007-04-02
Category: PUBLICATION
Original language: en
Available languages: en
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