DocumentCode :
1361831
Title :
Beamline Optimization for 100-keV Diagnostic Neutral Beam Injector for ITER
Author :
Bandyopadhyay, Mainak ; Singh, M.J. ; Rotti, Chandramouli ; Chakraborty, Arun ; Hemsworth, Ronald Stephen ; Schunke, Beatrix
Author_Institution :
Inst. for Plasma Res., ITER-India, Gandhinagar, India
Volume :
38
Issue :
3
fYear :
2010
fDate :
3/1/2010 12:00:00 AM
Firstpage :
242
Lastpage :
247
Abstract :
The 100-kV negative-hydrogen-ion-source-based diagnostic neutral beam (NB) (DNB) injector, which forms a part of the Indian (IN) procurement package for ITER, targets a delivery of ~18-20 A of neutral hydrogen-atom beam current into the ITER torus for charge exchange resonance spectroscopy diagnostics. Considering stripping losses, a ~70-A negative ion current is required to be extracted from the ion source, which leads to a production of 60 A of accelerated ion beam. Subsequent process of neutralization, electrostatic ion separation, and transport to the duct leads to a large separation between the points of generation of the ion beam to the point of delivery of the NB into the torus (~23 m). This forms one of the most important constraints for the transport of NBs to ITER. The requirements are not only for a stringent control over ion optics, the transport to electrostatic separator, minimum loss of beam due to intercepting elements, low reionization loss, and focusing to control interception losses but also for adequate compensation of residual magnetic fields to overcome magnetic field induced deflections also form important design issues for a reasonable transmission efficiency. Due to multiparameter dependence, it becomes necessary to assess the different scenarios using numerical codes. In the present case, the assessment has been carried out for the DNB using the beam-transport codes PDP, BTR, and the MCGF codes which are developed by the Russian Federation. An optimized configuration of the beamline has been arrived at on the basis of these code-enabled studies. These parameters are the following: listing of the vertical and horizontal focal lengths as 20.6 m, a spacing between ground grid and neutralizer of 1 m, and positioning of residual-ion dump at a distance of 0.75 m from the neutralizer exit. Further, optimizing the gas feed to the source and neutralizer leads to a final transmission of ~35% of the extracted beam power to the torus. This paper shall - - present the methodology, the issues concerned, and the final configuration which forms the basis for the present engineering.
Keywords :
Tokamak devices; charge exchange; ion sources; optimisation; plasma beam injection heating; plasma toroidal confinement; BTR codes; ITER torus; MCGF codes; PDP codes; beam transport codes; beamline optimization; charge exchange resonance spectroscopy diagnostics; diagnostic neutral beam injector; electron volt energy 100 keV; electrostatic ion separation; electrostatic separator; interception losses; ion optics; magnetic field induced deflections; negative hydrogen ion source; neutralization; reionization loss; residual magnetic field compensation; stripping losses; transmission efficiency; Beamline components (BLCs); ITER; beam transmission; diagnostic; neutral beam (NB);
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2009.2035623
Filename :
5357400
Link To Document :
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