2D divertor design calculations for the national high-power advanced torus experiment

J. M. Canik, R. Maingi, L. Owen, J. Menard, Robert James Goldston, M. Kotschenreuther, P. Valanju, S. Mahajan

Research output: Contribution to journalArticle

6 Scopus citations

Abstract

The national high-power advanced torus experiment is a concept for a new facility to address the FESAC theme of 'taming the plasma-material interface'. This concept exploits the compactness and excellent access provided by low aspect ratio to achieve a high ratio of exhaust power to major radius in order to study the integration of high-performance, long-pulse plasmas with a reactor-relevant high heat flux plasma boundary. Predictions of the scrape-off-layer plasma characteristics are presented, as calculated with the 2D edge modeling code SOLPS. Calculations in a variety of magnetic geometries indicate that very high levels of divertor heat flux can be expected, with peak values far in excess of the power handling capabilities of presently-used materials. Possible methods to reduce the heat flux to acceptable levels are discussed.

Original languageEnglish (US)
Pages (from-to)315-318
Number of pages4
JournalJournal of Nuclear Materials
Volume390-391
Issue number1
DOIs
StatePublished - Jun 15 2009

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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    Canik, J. M., Maingi, R., Owen, L., Menard, J., Goldston, R. J., Kotschenreuther, M., Valanju, P., & Mahajan, S. (2009). 2D divertor design calculations for the national high-power advanced torus experiment. Journal of Nuclear Materials, 390-391(1), 315-318. https://doi.org/10.1016/j.jnucmat.2009.01.143