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Horacek, J. [Author]; Pitts, R. A. [Author]; Hong, S-H [Author]; Janky, F. [Author]; LaBombard, B. [Author]; Marsen, S. [Author]; Maddaluno, G. [Author]; Nie, L. [Author]; Pericoli, V. [Author]; Popov, Tsv [Author]; Panek, R. [Author]; Rudakov, D. [Author]; Adamek, J. [Author]; Seidl, J. [Author]; Seo, D. S. [Author]; Shimada, M. [Author]; Silva, C. [Author]; Stangeby, P. C. [Author]; Viola, B. [Author]; Vondracek, P. [Author]; Wang, H. [Author]; Xu, G. S. [Author]; Xu, Y. [Author]; Arnoux, G. [Author]; [...]

Multi-machine scaling of the main SOL parallel heat flux width in tokamak limiter plasmas

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  • Media type: E-Article
  • Title: Multi-machine scaling of the main SOL parallel heat flux width in tokamak limiter plasmas
  • Contributor: Horacek, J. [Author]; Pitts, R. A. [Author]; Hong, S-H [Author]; Janky, F. [Author]; LaBombard, B. [Author]; Marsen, S. [Author]; Maddaluno, G. [Author]; Nie, L. [Author]; Pericoli, V. [Author]; Popov, Tsv [Author]; Panek, R. [Author]; Rudakov, D. [Author]; Adamek, J. [Author]; Seidl, J. [Author]; Seo, D. S. [Author]; Shimada, M. [Author]; Silva, C. [Author]; Stangeby, P. C. [Author]; Viola, B. [Author]; Vondracek, P. [Author]; Wang, H. [Author]; Xu, G. S. [Author]; Xu, Y. [Author]; Arnoux, G. [Author]; [...]
  • imprint: IOP Publ., 2016
  • Published in: Plasma physics and controlled fusion 58(7), 074005 - (2016). doi:10.1088/0741-3335/58/7/074005
  • Language: English
  • DOI: https://doi.org/10.1088/0741-3335/58/7/074005
  • ISSN: 0368-3281; 0032-1028; 1879-2979; 1361-6587; 0741-3335
  • Origination:
  • Footnote: Diese Datenquelle enthält auch Bestandsnachweise, die nicht zu einem Volltext führen.
  • Description: As in many of today's tokamaks, plasma start-up in ITER will be performed in limiter configuration on either the inner or outer midplane first wall (FW). The massive, beryllium armored ITER FW panels are toroidally shaped to protect panel-to-panel misalignments, increasing the deposited power flux density compared with a purely cylindrical surface. The chosen shaping should thus be optimized for a given radial profile of parallel heat flux, ${{q}_{||}}$ in the scrape-off layer (SOL) to ensure optimal power spreading. For plasmas limited on the outer wall in tokamaks, this profile is commonly observed to decay exponentially as ${{q}_{||}}={{q}_{0}}\text{exp} ~\left(-r/\lambda _{q}^{\text{omp}}\right)$ , or, for inner wall limiter plasmas with the double exponential decay comprising a sharp near-SOL feature and a broader main SOL width, $\lambda _{q}^{\text{omp}}$ . The initial choice of $\lambda _{q}^{\text{omp}}$ , which is critical in ensuring that current ramp-up or down will be possible as planned in the ITER scenario design, was made on the basis of an extremely restricted L-mode divertor dataset, using infra-red thermography measurements on the outer divertor target to extrapolate to a heat flux width at the main plasma midplane. This unsatisfactory situation has now been significantly improved by a dedicated multi-machine ohmic and L-mode limiter plasma study, conducted under the auspices of the International Tokamak Physics Activity, involving 11 tokamaks covering a wide parameter range with $R=\text{0}\text{.4--2}\text{.8}\,\text{m},\,{{B}_{0}}=\text{1}\text{.2--7}\text{.5}\,\text{T},\,{{I}_{\text{p}}}=\text{9--2500}\,\text{kA}.$ Measurements of $\lambda _{q}^{\text{omp}}$ in the database are made exclusively on all devices using a variety of fast reciprocating Langmuir probes entering the plasma at a variety of poloidal locations, but with the majority being on the low field side. Statistical analysis of the database reveals nine reasonable engineering and dimensionless scalings. All yield, however, ...
  • Access State: Open Access