Tokamak edge model validation and improvement

D. P. Coster, J. W. Kim, Y. Nishimura, R. Schneider, X. Bonnin, V. Rozhansky, S. Voskoboynikov

Research output: Contribution to journalConference article

10 Citations (Scopus)

Abstract

Because of the complexity of the physics in the edge of divertor tokamaks, extrapolation from present-day machines to future reactor or reactor-type devices is done using two-dimensional-edge codes. Amongst the issues which are important for future machines, are those of inboard/outboard divertor power asymmetries and the compression of hydrogen and helium. The issues driving the in-out power asymmetry are explored, and a reasonable match is found to existing experiments, as well as an 'adjustable knob' that could be used to further improve the match. In this work, one further effect that is known to play a role-that of E × B and diamagnetic drifts-is identified but not analysed, because the codes have not yet been able to include the drift terms in combination with the impurities and kinetic neutrals. It is also shown that the codes reproduce the fact the only small differences were seen on the ASDEX Upgrade experiment in the compression of helium when the DivII divertor was replaced by the DivIIb configuration.

Original languageEnglish
Article number323
Pages (from-to)979-984
Number of pages6
JournalPlasma Physics and Controlled Fusion
Volume44
Issue number6
DOIs
Publication statusPublished - 2002 Jun
EventIAEA Technical Committee Meeting on Divertor Concepts - Aix-en-Provence, France
Duration: 2001 Sep 112001 Sep 14

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Condensed Matter Physics

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    Coster, D. P., Kim, J. W., Nishimura, Y., Schneider, R., Bonnin, X., Rozhansky, V., & Voskoboynikov, S. (2002). Tokamak edge model validation and improvement. Plasma Physics and Controlled Fusion, 44(6), 979-984. [323]. https://doi.org/10.1088/0741-3335/44/6/323