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.
| Original language | English |
|---|---|
| Pages (from-to) | 1387-1392 |
| Number of pages | 6 |
| Journal | IEEE Transactions on Plasma Science |
| Volume | 46 |
| Issue number | 5 |
| DOIs | |
| State | Published - May 2018 |
Funding
Manuscript received June 21, 2017; revised October 5, 2017; accepted November 24, 2017. Date of publication December 18, 2017; date of current version May 8, 2018. This work was supported in part by the U.S. Department of Energy, UT-Battelle, LLC under Contract DE-AC05-00OR22725 and in part by the framework of the EUROfusion Consortium through the Euratom Research and Training Program 2014\u20132018 under Grant 633053. The review of this paper was arranged by Senior Editor E. Surrey. (Corresponding author: J. D. Lore.) J. D. Lore and M. Cianciosa are with the Oak Ridge National Laboratory, Oak Ridge, TN 37831 USA (e-mail: [email protected]).
Keywords
- Fusion reactors
- Plasma simulation
- Plasma transport processes
- Wendelstein 7-X (W7-X)