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Disruptions in ITER and strategies for their control and mitigation

  • M. Lehnen
  • , K. Aleynikova
  • , P. B. Aleynikov
  • , D. J. Campbell
  • , P. Drewelow
  • , N. W. Eidietis
  • , Yu Gasparyan
  • , R. S. Granetz
  • , Y. Gribov
  • , N. Hartmann
  • , E. M. Hollmann
  • , V. A. Izzo
  • , S. Jachmich
  • , S. H. Kim
  • , M. Kočan
  • , H. R. Koslowski
  • , D. Kovalenko
  • , U. Kruezi
  • , A. Loarte
  • , S. Maruyama
  • G. F. Matthews, P. B. Parks, G. Pautasso, R. A. Pitts, C. Reux, V. Riccardo, R. Roccella, J. A. Snipes, A. J. Thornton, P. C. De Vries
  • ITER
  • Max-Planck-Institut für Plasmaphysik
  • General Atomics
  • National Research Nuclear University MEPhI
  • MIT Plasma Science and Fusion Center
  • FORSCHUNGSZENTRUM JULICH GMBH
  • University of California, San Diego
  • Troitsk Insitute of Innovating and Thermonuclear Research (TRINITI)
  • Culham Centre for Fusion Energy
  • Commissariat à l'Énergie Atomique (CEA)

Résultats de recherche: Contribution à un journalArticleRevue par des pairs

415 Citations (Scopus)

Résumé

Abstract The thermal and electromagnetic loads related to disruptions in ITER are substantial and require careful design of tokamak components to ensure they reach the projected lifetime and to ensure that safety relevant components fulfil their function for the worst foreseen scenarios. The disruption load specifications are the basis for the design process of components like the full-W divertor, the blanket modules and the vacuum vessel and will set the boundary conditions for ITER operations. This paper will give a brief overview on the disruption loads and mitigation strategies for ITER and will discuss the physics basis which is continuously refined through the current disruption R&D programs.

langue originaleAnglais
Numéro d'article48572
Pages (de - à)39-48
Nombre de pages10
journalJournal of Nuclear Materials
Volume463
Les DOIs
étatPublié - 22 juil. 2015

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