Minimum magnetic curvature for resilient divertors using Compact Toroidal Hybrid geometry
Abstract
The properties of resilient divertors are explored using equilibria derived from Compact Toroidal Hybrid (CTH) geometries. Resilience is defined here as the robustness of the strike point patterns as the plasma geometry and/or plasma profiles are changed. The addition of plasma current in the CTH configurations significantly alters the shape of the last closed flux surface and the rotational transform profile, however, it does not alter the strike point pattern on the target plates, and hence has resilient divertor features. The limits of when a configuration transforms to a resilient configuration is then explored. New CTH-like configurations are generated that vary from a perfectly circular cross section to configurations with increasing amounts of toroidal shaping. It is found that even small amounts of toroidal shaping lead to strike point localization that is similar to the standard CTH configuration. Lastly, these results show that only a small degree of three-dimensional shaping is necessary to produce a resilient divertor, implying that any highly shaped optimized stellarator will possess the resilient divertor property.
- Authors:
-
[1];
[2];
- Univ. of Wisconsin, Madison, WI (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Auburn Univ., AL (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1426567
- Grant/Contract Number:
- AC05-00OR22725; FG02-93ER54222
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Plasma Physics and Controlled Fusion
- Additional Journal Information:
- Journal Volume: 60; Journal Issue: 5; Journal ID: ISSN 0741-3335
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; stellarator; divertor; resilient; CTH
Citation Formats
Bader, Aaron, Hegna, C. C., Cianciosa, Mark R., and Hartwell, G. J. Minimum magnetic curvature for resilient divertors using Compact Toroidal Hybrid geometry. United States: N. p., 2018.
Web. doi:10.1088/1361-6587/aab1ea.
Bader, Aaron, Hegna, C. C., Cianciosa, Mark R., & Hartwell, G. J. Minimum magnetic curvature for resilient divertors using Compact Toroidal Hybrid geometry. United States. https://doi.org/10.1088/1361-6587/aab1ea
Bader, Aaron, Hegna, C. C., Cianciosa, Mark R., and Hartwell, G. J. Fri .
"Minimum magnetic curvature for resilient divertors using Compact Toroidal Hybrid geometry". United States. https://doi.org/10.1088/1361-6587/aab1ea. https://www.osti.gov/servlets/purl/1426567.
@article{osti_1426567,
title = {Minimum magnetic curvature for resilient divertors using Compact Toroidal Hybrid geometry},
author = {Bader, Aaron and Hegna, C. C. and Cianciosa, Mark R. and Hartwell, G. J.},
abstractNote = {The properties of resilient divertors are explored using equilibria derived from Compact Toroidal Hybrid (CTH) geometries. Resilience is defined here as the robustness of the strike point patterns as the plasma geometry and/or plasma profiles are changed. The addition of plasma current in the CTH configurations significantly alters the shape of the last closed flux surface and the rotational transform profile, however, it does not alter the strike point pattern on the target plates, and hence has resilient divertor features. The limits of when a configuration transforms to a resilient configuration is then explored. New CTH-like configurations are generated that vary from a perfectly circular cross section to configurations with increasing amounts of toroidal shaping. It is found that even small amounts of toroidal shaping lead to strike point localization that is similar to the standard CTH configuration. Lastly, these results show that only a small degree of three-dimensional shaping is necessary to produce a resilient divertor, implying that any highly shaped optimized stellarator will possess the resilient divertor property.},
doi = {10.1088/1361-6587/aab1ea},
journal = {Plasma Physics and Controlled Fusion},
number = 5,
volume = 60,
place = {United States},
year = {Fri Mar 16 00:00:00 EDT 2018},
month = {Fri Mar 16 00:00:00 EDT 2018}
}
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Figures / Tables:
FIG. 1: The CTH coil-set is shown with the helical coil (blue), the vertical field coils (red) and the toroidal field coils (black) b) The plasma vacuum equilibrium created with only the helical and vertical field coils is shown. The colored contour represents the magnetic field strength.
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Figures / Tables found in this record:
Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.