Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements
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.
- Authors:
-
[1];
[1];
[3];
[3]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Univ. of Wisconsin, Madison, WI (United States)
- Max Planck Institute for Plasma Physics, Greifswald (Germany)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC)
- OSTI Identifier:
- 1488732
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- IEEE Transactions on Plasma Science
- Additional Journal Information:
- Journal Volume: 46; Journal Issue: 5; Journal ID: ISSN 0093-3813
- Publisher:
- IEEE
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Fusion reactors; plasma simulation; plasma transport processes; Wendelstein 7-X (W7-X)
Citation Formats
Lore, Jeremy D., Cianciosa, Mark R., Frerichs, Heinke, Geiger, J., Hoelbe, H., and Boscary, J. Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements. United States: N. p., 2017.
Web. doi:10.1109/TPS.2017.2780624.
Lore, Jeremy D., Cianciosa, Mark R., Frerichs, Heinke, Geiger, J., Hoelbe, H., & Boscary, J. Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements. United States. https://doi.org/10.1109/TPS.2017.2780624
Lore, Jeremy D., Cianciosa, Mark R., Frerichs, Heinke, Geiger, J., Hoelbe, H., and Boscary, J. Mon .
"Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements". United States. https://doi.org/10.1109/TPS.2017.2780624. https://www.osti.gov/servlets/purl/1488732.
@article{osti_1488732,
title = {Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements},
author = {Lore, Jeremy D. and Cianciosa, Mark R. and Frerichs, Heinke and Geiger, J. and Hoelbe, H. and Boscary, J.},
abstractNote = {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.},
doi = {10.1109/TPS.2017.2780624},
journal = {IEEE Transactions on Plasma Science},
number = 5,
volume = 46,
place = {United States},
year = {Mon Dec 18 00:00:00 EST 2017},
month = {Mon Dec 18 00:00:00 EST 2017}
}
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Cited by: 10 works
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Figures / Tables:
Fig. 1.: Primary components of a W7-X divertor unit, from [7].
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Works referencing / citing this record:
Measurement and modeling of magnetic configurations to mimic overload scenarios in the W7-X stellarator
journal, May 2019
- Lore, J. D.; Gao, Y.; Geiger, J.
- Nuclear Fusion, Vol. 59, Issue 6
First divertor physics studies in Wendelstein 7-X
journal, July 2019
- Sunn Pedersen, T.; König, R.; Jakubowski, M.
- Nuclear Fusion, Vol. 59, Issue 9
Effects of toroidal plasma current on divertor power depositions on Wendelstein 7-X
journal, August 2019
- Gao, Yu; Geiger, Joachim; Jakubowski, Marcin W.
- Nuclear Fusion, Vol. 59, Issue 10
Scenario with combined density and heating control to reduce the impact of the bootstrap current in Wendelstein 7-X
journal, September 2019
- Sinha, P.; Böckenhoff, D.; Endler, M.
- Nuclear Fusion, Vol. 59, Issue 12
Figures / Tables found in this record:
Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.