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

Journal Article · Mon Dec 18 00:00:00 EST 2017 · IEEE Transactions on Plasma Science

DOI:https://doi.org/10.1109/TPS.2017.2780624· OSTI ID:1488732

Lore, Jeremy D.  ^[1]; Cianciosa, Mark R.  ^[1]; Frerichs, Heinke ^[2]; Geiger, J.  ^[3]; Hoelbe, H. ^[3]; Boscary, J.  ^[3]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Univ. of Wisconsin, Madison, WI (United States)
3. Max Planck Institute for Plasma Physics, Greifswald (Germany)

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1488732
• Journal Information: IEEE Transactions on Plasma Science, Vol. 46, Issue 5; ISSN 0093-3813
• Publisher: IEEE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Fusion reactors
plasma simulation
plasma transport processes
Wendelstein 7-X (W7-X)