Helium neutral beam injection into ASDEX Upgrade

被引:4
作者
Hopf, C. [1 ]
Rittich, D. [1 ]
Schaeffler, J. [1 ]
Thalhammer, J. [1 ]
机构
[1] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany
关键词
Neutral beam injection; Helium; ASDEX Upgrade; DESIGN;
D O I
10.1016/j.fusengdes.2017.05.052
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
ASDEX Upgrade's (AUG) neutral beam injection (NBI) system is primarily designed for deuterium injection and delivers 20 MW heating power from two injectors with four beams each at 60 and 93 keV, respectively. As opposed to the cryo pumps of the JET NBI, the Ti getter pumps of the AUG NBI with a pumping speed of 3 x 10(6) l/s for hydrogen do not pump helium at all, leaving only the conventional pumping system with <6 x10(3) l/s for He. This imposes constraints on the possible operation in helium. In order to prepare for AUG He plasma campaigns, serious trials to operate the AUG NBI with He began in 2014. It was found that despite the lack of high speed pumping up to two beams per injector could be operated simultaneously at reduced feed gas flow without particular restrictions on the beam-on time. For injector 1 the power per beam was limited to 550 kW at 40 keV by the required filament current in its arc sources, while for injector 2 the limitation came from the bending magnet's power supply that restricted the beam energy to 68 keV and the NBI power to 730 kW per beam. Thus the maximum available NBI heating power in He amounts to 2.6 MW for 10 s, the maximum discharge duration of AUG. Helium neutral beam injection into plasma was first tried out in 2014 for two discharges. In 2015 a dedicated He campaign used He NBI in a total of 44 discharges. As He is almost not pumped in the injectors the neutral gas flow into the torus is comparable with the total He gas puff. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:281 / 284
页数:4
相关论文
共 10 条
[2]   Feasibility of non-thermal helium measurements with charge exchange spectroscopy on ITER [J].
Kappatou, A. ;
Delabie, E. ;
Jaspers, R. J. E. ;
von Hellermann, M. G. .
NUCLEAR FUSION, 2012, 52 (04)
[3]  
Kappatou A., 2014, THESIS
[4]  
MARCUS FB, 1992, PLASMA PHYS CONTR F, V34, P1371, DOI 10.1088/0741-3335/34/8/001
[5]  
McDonald D. C., 2004, PLASMA PHYS CONTROL, V46
[6]   AC operation of large titanium sublimation pumps in a magnetic field: Results of the test stand for the W7-X neutral beam injectors [J].
Orozco, G. ;
Froeschle, M. ;
Heinemann, B. ;
Hopf, C. ;
Nocentini, R. ;
Riedl, R. ;
Staebler, A. .
FUSION ENGINEERING AND DESIGN, 2014, 89 (12) :3070-3077
[7]  
Phillips J. C., 1995, P 16 IEEE NPSS S FUS, P852
[8]   Rf ion sources for fusion applications: design, development and performance [J].
Speth, E ;
Ciric, M ;
Feist, JH ;
Frank, P ;
Heinemann, B ;
Kraus, W ;
Probst, F ;
Riedl, R ;
Trainham, R ;
Vollmer, O ;
Wilhelm, R .
FUSION ENGINEERING AND DESIGN, 1999, 46 (2-4) :383-388
[9]   Chapter 2:: Machine design, fueling, and heating in ASDEX upgrade [J].
Streibl, B ;
Lang, PT ;
Leuterer, F ;
Noterdaeme, JM ;
Stäbler, A .
FUSION SCIENCE AND TECHNOLOGY, 2003, 44 (03) :578-592
[10]   OBSERVATION OF ALPHA-PARTICLE SLOWING-DOWN SPECTRA IN JET HELIUM BEAM FUELING AND HEATING EXPERIMENTS [J].
VONHELLERMAN, MG ;
CORE, WGF ;
FRIELING, J ;
HORTON, LD ;
KONIG, RWT ;
MANDL, W ;
SUMMERS, HP .
PLASMA PHYSICS AND CONTROLLED FUSION, 1993, 35 (07) :799-824