Published June 2009 | Version v1
Journal article

The ITER full size plasma source device design

Description

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. The main design choices will be presented in the paper as well as an overview of the design of the main components and systems.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2008.11.095

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2008.11.095;
PII
S0920-3796(08)00412-2;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
84
Journal Issue
2-6
Journal Page Range
p. 269-274
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
25. symposium on fusion technology
Acronym
SOFT-25
Dates
15-19 Sep 2008
Place
Rostock (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41031120
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; ITER TOKAMAK; NEUTRAL ATOM BEAM INJECTION; PLASMA; TEST FACILITIES
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.