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  Development of active control systems on ASDEX upgrade in view of ITER discharge scenarios

Mertens, V., Hobirk, J., Kallenbach, A., Lang, P., Mück, A., Pautasso, G., et al. (2003). Development of active control systems on ASDEX upgrade in view of ITER discharge scenarios. Fusion Engineering and Design, 66-68, 119-127. doi:10.1016/S0920-3796(03)00144-3.

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Item Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-239B-1 Version Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-23A6-7
Genre: Journal Article

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 Creators:
Mertens, V.1, Author              
Hobirk, J.1, Author              
Kallenbach, A.2, Author              
Lang, P.1, Author              
Mück, A.3, Author              
Pautasso, G.4, Author              
Raupp, G.5, Author              
Sips, A.1, Author              
Stober, J.1, Author              
Zohm, H.5, Author              
ASDEX Upgrade Team, Author  
Affiliations:
1Experimental Plasma Physics 1 (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856295              
2Experimental Plasma Physics 4 (E4), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856293              
3External Organizations, ou_persistent22              
4Tokamak Theory (TOK), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856309              
5Experimental Plasma Physics 2 (E2), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856292              

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Free keywords: 22nd Symposium on Fusion Technology (SOFT 2002), Helsinki, 2002-09-09 to 2002-09-13
 Abstract: ASDEX Upgrade has a large variety of technical systems, heating and fuelling as well as digital control systems needed for control and optimisation of high performance plasmas. The neutral beam injection (NBI), electron cyclotron RF (ECRF) and ion cyclotron resonance frequency (ICRF) heating systems are able to operate in heating as well as in current drive (CD) mode. One of two NBI systems has recently been redirected to allow more tangential injection to provide larger CD efficiency. With improved control procedures significant success is achieved in the optimisation of the conventional H-mode (ITER reference scenario) as well as of `advanced tokamak' scenarios. The established operational boundaries encounter or exceed those of the reference scenario. H-modes showing type II ELMs with clearly reduced peak power loads on the target plates are produced at densities close to the empirical Greenwald density limit. Discharges with nearly full non-inductively driven plasma current at Greenwald densities are performed. MHD instabilities like sawteeth and neoclassical tearing modes (NTM) can be tailored and/or completely be stabilised via electron cyclotron frequency CD at relatively low injection power levels. In addition, several non-standard feedback control circuits for plasma performance improvements and machine protection circuits are devised.

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Language(s): eng - English
 Dates: 2003
 Publication Status: Published in print
 Pages: -
 Publishing info: -
 Table of Contents: -
 Rev. Type: Peer
 Degree: -

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Title: Fusion Engineering and Design
  Alternative Title : Fusion Eng. Des.
Source Genre: Journal
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Publ. Info: Copyright © 2003 Elsevier B.V. All rights reserved
Pages: - Volume / Issue: 66-68 Sequence Number: - Start / End Page: 119 - 127 Identifier: -