Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements

Content Provider	United States Department of Energy Office of Scientific and Technical Information (OSTI.GOV)
Author	Lore, Jeremy D. Frerichs, Heinke Geiger, J. Hoelbe, H. Boscary, J.
Organization	Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Abstract	Simulations of heat fluxes to the plasma facing components in the Wendelstein 7-X stellarator will be tested in its next operational phase. The simulations consist of core transport calculations that determine the evolution of the kinetic profiles and the toroidal current, which modifies the fluxes to the divertor, as the magnetic geometry changes. An additional divertor component, the scraper element, was designed to protect the edges of the primary divertor throughout this evolution during certain high-power long-pulse operational scenarios. The effect of unknown parameters of the heat flux calculations, namely, the cross-field thermal diffusivity and the magnetic field structure, is explored. The predicted scaling of the heat flux widths and magnitudes is presented, along with a new method of calculating the 3-D magnetic field structure required to perform the flux calculations.
Sponsorship	USDOE Office of Science (SC)
Related Links	https://www.osti.gov/biblio/1488732
Starting Page	1387
Ending Page	1392
Page Count	6
File Format	PDF
ISSN	00933813
DOI	10.1109/TPS.2017.2780624
Journal	IEEE Transactions on Plasma Science
Volume Number	46
Issue Number	5
Language	English
Publisher	IEEE
Publisher Date	2017-12-18
Publisher Place	United States
Access Restriction	Open
Subject Keyword	PLASMA PHYSICS AND FUSION TECHNOLOGY Fusion reactors plasma simulation plasma transport processes Wendelstein 7-X (W7-X)
Content Type	Text
Resource Type	Article
Subject	Nuclear and High Energy Physics Condensed Matter Physics