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  Assessment of the W7-X high heat flux divertor with thermo-mechanical analysis

Qian, X., Peng, X., Fellinger, J., Boscary, J., Bykov, V., Wang, Z., et al. (2016). Assessment of the W7-X high heat flux divertor with thermo-mechanical analysis. Fusion Engineering and Design, 109-111, Pt. A, 565-568. doi:10.1016/j.fusengdes.2016.02.045.

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 Creators:
Qian, X.1, Author
Peng, X.1, Author
Fellinger, J.2, Author           
Boscary, J.3, Author           
Bykov, V.4, Author           
Wang, Z.1, Author
Ye, M.1, Author
Song, Y.1, Author
Affiliations:
1External Organizations, ou_persistent22              
2Stellarator Edge and Divertor Physics (E4), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856286              
3Tokamak Scenario Development (E1), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856321              
4W7-X: Operations (OP), Max Planck Institute for Plasma Physics, Max Planck Society, ou_1856342              

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Free keywords: Konferenzbeitrag
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Language(s): eng - English
 Dates: 20152016
 Publication Status: Issued
 Pages: -
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 Table of Contents: -
 Rev. Type: Peer
 Identifiers: DOI: 10.1016/j.fusengdes.2016.02.045
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Title: Fusion Engineering and Design
  Subtitle : 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), Jeju Island, 2015-09-14 to 2015-09-18
Source Genre: Journal
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Publ. Info: Amsterdam : Elsevier B.V.
Pages: - Volume / Issue: 109-111, Pt. A Sequence Number: - Start / End Page: 565 - 568 Identifier: ISSN: 0920-3796
CoNE: https://pure.mpg.de/cone/journals/resource/954925564661