ISSN:
1089-7623
Quelle:
AIP Digital Archive
Thema:
Physik
,
Elektrotechnik, Elektronik, Nachrichtentechnik
Notizen:
Neutral beam injection systems (NBI) are capable of injecting powers greater than 20 MW, with pulse length of 5 s. These systems, based on acceleration and neutralization of positive deuterium ions, provide heating and current drive capability and are highly reliable and available. For possible application to a "next step'' fusion device (ITER or NET), a large extrapolation of neutral deuterium energy is necessary to sustain a noninductively driven toroidal current. For good electrical efficiency of these injectors, the choice of acceleration and neutralization of deuterium negative ions beams is an attractive option. A conceptual European design for ITER/NET is proposed with a pure D− ion source (15 A) biased at a high voltage of −1 MV, a multistage electrostatic accelerator with multihole apertures, a grounded gas neutralizer and an electrostatic deflection beam dump. Special supplies are being studied in order to energize the accelerator (1 MV–15 A) with low stored energy and fast switch off time during a fault in the accelerator. By using nine similar injectors, a neutral power of 75 MW can be installed to drive the ITER current. The expected efficiency is better than 40%. A scalable model (4-A D−, 1 MV) to produce a power of 2-MW D0 can be in operation in 1995. The main areas of uncertainty (D− source, electron trapping, large power accelerator, breakdowns, and power supplies) will be studied with this scalable model. When this first phase has been achieved, the final-size injector will be built.
Materialart:
Digitale Medien
URL:
http://dx.doi.org/10.1063/1.1142867
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