DocumentCode :
300993
Title :
Beta normal limiting of TFTR neutral beams
Author :
Lawson, J.E. ; Bell, M.G. ; Marsala, R.J. ; Mueller, D.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Volume :
1
fYear :
1995
fDate :
30 Sep-5 Oct 1995
Firstpage :
526
Abstract :
In TFTR plasmas heated by neutral beam injection, the fusion power yield increases rapidly with the plasma pressure. However, the pressure is limited by the onset of instabilities which may result in plasma disruptions that increase the risk of damage to internal components. The likelihood of disruption has been found to correlate with the normalized beta (βN). For TFTR plasmas with high fusion performance (TFTR “supershots”) this probability of disruption has been found to increase rapidly. Since confinement in this regime is affected by plasma-wall interaction, which can vary from shot to shot, operation at high βN with preprogrammed heating power pulses can produce an unacceptably high risk of disruption. To reduce the risk of producing beta-limit disruptions during neutral beam heating experiments, a control system, the Neutral Beam Power Feedback System (NBPFS), has been developed to modulate the total heating power by switching individual neutral beam sources on and off in response to the evolution of the normalized beta so that the limit will not be exceeded. The value of βN is calculated in real time and transmitted to the NBPFS. The value of βN and its calculated time derivative are input to a fuzzy logic controller which implements a proportional-derivative control based on the difference between βN and a programmed reference level βNREF which is programmed as a function of time. The output of the controller is a set of twelve signals, one for each neutral beam source, which can block injection. These signals are updated every 10 ms in response to the plasma behaviour. The tokamak operators specify the order in which sources will be turned off and on as the βN limit is approached. The system has been in operation since May 1994 and has shown that the βN can be controlled and that the neutral beam sources can operate reliably with this 10 ms modulation
Keywords :
Tokamak devices; fusion reactor operation; fuzzy control; plasma beam injection heating; temperature control; two-term control; Neutral Beam Power Feedback System; TFTR neutral beams; beta normal limiting; fusion power yield; fuzzy logic controller; neutral beam injection; plasma behaviour; plasma disruptions; plasma-wall interaction; programmed reference level; Control systems; Feedback; Fuzzy logic; Heating; Optical modulation; PD control; Particle beam injection; Particle beams; Plasma confinement; Temperature control;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
Type :
conf
DOI :
10.1109/FUSION.1995.534275
Filename :
534275
Link To Document :
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