Title of article :
The ITER full size plasma source device design
Author/Authors :
Sonato، نويسنده , , P. and Agostinetti، نويسنده , , P. and Anaclerio، نويسنده , , G. and Antoni، نويسنده , , V. and Barana، نويسنده , , O. and Bigi، نويسنده , , M. and Boldrin، نويسنده , , M. and Cavenago، نويسنده , , M. and Dal Bello، نويسنده , , S. Di Palma، نويسنده , , M. Dalla and Daniele، نويسنده , , A. and D’Arienzo، نويسنده , , M. and De Lorenzi، نويسنده , , A. and Ferro، نويسنده , , A. and Fiorentin، نويسنده , , A. and Gaio، نويسنده , , E. and Gazza، نويسنده , , E. and Grando، نويسنده , , L. and Fantini، نويسنده , , F. and Fellin، نويسنده , , F. and Luchetta، نويسنده , , A. and Manduchi، نويسنده , , G. and Milani، نويسنده , , F. and Marcuzzi، نويسنده , , D. and Novello، نويسنده , , L. and Pasqualotto، نويسنده , , R. and Pavei، نويسنده , , M. and Pengo، نويسنده , , R. and Peruzzo، نويسنده , , S. and Pesce، نويسنده , , A. and Pilan، نويسنده , , N. and Piovan، نويسنده , , R. and Pomaro، نويسنده , , N. and Recchia، نويسنده , , M. and Rigato، نويسنده , , W. and Rizzolo، نويسنده , , A. and Serianni، نويسنده , , G. and Spolaore، نويسنده , , M. and Spolaore، نويسنده , , P. Levi Sandri، نويسنده , , S. and Taliercio، نويسنده , , C. and Toigo، نويسنده , , V. and Valisa، نويسنده , , Christie M. and Veltri، نويسنده , , P. and Zaccaria، نويسنده , , P. and Zamengo، نويسنده , , A. and Zanotto، نويسنده , , L.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2009
Pages :
6
From page :
269
To page :
274
Abstract :
In the framework of the strategy for the development and the procurement of the NB systems for ITER, it has been decided to build in Padova a test facility, including two experimental devices: a full size plasma source with low voltage extraction and a full size NB injector at full beam power (1 MV). These two different devices will separately address the main scientific and technological issues of the 17 MW NB injector for ITER. In particular the full size plasma source of negative ions will address the ITER performance requirements in terms of current density and uniformity, limitation of the electron/ion ratio and stationary operation at full current with high reliability and constant performances for the whole operating time up to 1 h. The required negative ion current density to be extracted from the plasma source ranges from 290 A/m2 in D2 (D−) and 350 A/m2 in H2 (H−) and these values should be obtained at the lowest admissible neutral pressure in the plasma source volume, nominally at 0.3 Pa. The electron to ion ratio should be limited to less than 1 and the admissible ion inhomogeneity extracted from the grids should be better than 10% on the whole plasma cross-section having a surface exposed to the extraction grid of the order of 1 m2. in design choices will be presented in the paper as well as an overview of the design of the main components and systems.
Keywords :
Neutral beam , ITER , rf source
Journal title :
Fusion Engineering and Design
Serial Year :
2009
Journal title :
Fusion Engineering and Design
Record number :
2355527
Link To Document :
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