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  The divertor program in stellarators

König, R., Grigull, P., McCormick, K., Feng, Y., Kisslinger, J., Komori, A., et al. (2002). The divertor program in stellarators. Plasma Physics and Controlled Fusion, 44(11), 2365-2422.

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Item Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-420B-6 Version Permalink: http://hdl.handle.net/11858/00-001M-0000-0027-420C-4
Genre: Journal Article

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König, R.1, Author              
Grigull, P.2, Author              
McCormick, K.1, Author              
Feng, Y.3, 4, Author              
Kisslinger, J.3, 4, Author              
Komori, A.5, Author
Masuzaki, S.5, Author
Matsuoka, K.5, Author
Obiki, T.5, Author
Ohyabu, N.5, Author
Renner, H.6, Author              
Sardei, F.3, Author              
Wagner, F.3, Author              
Werner, A.2, Author              
Affiliations:
1Stellarator Scenario Development (E5), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856285              
2W7-X: Physics (PH), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856305              
3Experimental Plasma Physics 3 (E3), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856291              
4W7-AS, Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856310              
5Natl Inst Fus Sci, Toki, Gifu 5098592, Japan; Kyoto Univ, Inst Adv Energy, Uji, Kyoto, Japan, ou_persistent22              
6W7-X: Construction, Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856314              

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 Abstract: Two significiant problems that need to be solved for any future fusion device are heat removal and particle control. A very promising method to attack these problems in tokamaks and helical devices is, the use of a divertor, providing a controlled interaction zone between plasma and wall. By carefully designing a divertor, conditions can be created in front of the divertor targets, which lead to a. sufficient reduction of the power load on the targets by strong radiation redistribution. Any solution of course I needs to allow for an energy confinement which is at least sufficient for the realization of a fusion reactor. Since energy confinement has been found to be strongly related to edge anomalous transport and edge plasma profiles,the ultimate aim is to find an integral solution which is optimum with respect to exhaust, heat load and energy confinement. Two different types of divertors are presently being investigated in helical devices: the 'helical divertor' and the 'island divertor'. So far divertor' concepts have been investigated only in a few helical devices. Theoretical and experimental efforts have mainly concentrated on the suitability of divertor magnetic field structures, While detailed studies of the divertor plasma properties for the two types of divertor configurations have only recently begun. In the course of this exploration, a promising new high-density H-mode (HDH) plasma operational regime has been discovered on the Wendelstein stellarator W7- AS. It benefits from high-energy (up to twice the value of the International Stellarator Scaling ISS95) and. low impurity confinement times, complemented by edge radiated power fractions of up to 90% in detached regimes. This allowed quasi- steady-state operation for up to 50 energy confinement times and so far was only constrained by machine operability.

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Language(s): eng - English
 Dates: 2002
 Publication Status: Published in print
 Pages: -
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 Table of Contents: -
 Rev. Type: Peer
 Identifiers: eDoc: 20700
ISI: 000179660600007
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Title: Plasma Physics and Controlled Fusion
  Alternative Title : Plasma Phys. Control. Fusion
Source Genre: Journal
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Pages: - Volume / Issue: 44 (11) Sequence Number: - Start / End Page: 2365 - 2422 Identifier: ISSN: 0741-3335