Numerical optimization of three-dimensional coils for NSTX-U
Abstract
A tool for the calculation of optimal three-dimensional (3D) perturbative magnetic fields in tokamaks has been developed. The IPECOPT code builds upon the stellarator optimization code STELLOPT to allow for optimization of linear ideal magnetohydrodynamic perturbed equilibrium (IPEC). This tool has been applied to NSTX-U equilibria, addressing which fields are the most effective at driving NTV torques. The NTV torque calculation is performed by the PENT code. Optimization of the normal field spectrum shows that fields with n = 1 character can drive a large core torque. It is also shown that fields with n = 3 features are capable of driving edge torque and some core torque. Coil current optimization (using the planned in-vessel and existing RWM coils) on NSTX-U suggest the planned coils set is adequate for core and edge torque control. In conclusion, comparison between error field correction experiments on DIII-D and the optimizer show good agreement.
- Authors:
-
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Columbia Univ., New York, NY (United States)
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- OSTI Identifier:
- 1255635
- Alternate Identifier(s):
- OSTI ID: 1238861
- Report Number(s):
- PPPL-5181
Journal ID: ISSN 0741-3335
- Grant/Contract Number:
- AC02-09CH11466
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Plasma Physics and Controlled Fusion
- Additional Journal Information:
- Journal Volume: 57; Journal Issue: 10; Journal ID: ISSN 0741-3335
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; tokamak; equilibrium; optimization; torque; rotation; in-vessel coils
Citation Formats
Lazerson, S. A., Park, J. -K., Logan, N., and Boozer, A. Numerical optimization of three-dimensional coils for NSTX-U. United States: N. p., 2015.
Web. doi:10.1088/0741-3335/57/10/104001.
Lazerson, S. A., Park, J. -K., Logan, N., & Boozer, A. Numerical optimization of three-dimensional coils for NSTX-U. United States. https://doi.org/10.1088/0741-3335/57/10/104001
Lazerson, S. A., Park, J. -K., Logan, N., and Boozer, A. Thu .
"Numerical optimization of three-dimensional coils for NSTX-U". United States. https://doi.org/10.1088/0741-3335/57/10/104001. https://www.osti.gov/servlets/purl/1255635.
@article{osti_1255635,
title = {Numerical optimization of three-dimensional coils for NSTX-U},
author = {Lazerson, S. A. and Park, J. -K. and Logan, N. and Boozer, A.},
abstractNote = {A tool for the calculation of optimal three-dimensional (3D) perturbative magnetic fields in tokamaks has been developed. The IPECOPT code builds upon the stellarator optimization code STELLOPT to allow for optimization of linear ideal magnetohydrodynamic perturbed equilibrium (IPEC). This tool has been applied to NSTX-U equilibria, addressing which fields are the most effective at driving NTV torques. The NTV torque calculation is performed by the PENT code. Optimization of the normal field spectrum shows that fields with n = 1 character can drive a large core torque. It is also shown that fields with n = 3 features are capable of driving edge torque and some core torque. Coil current optimization (using the planned in-vessel and existing RWM coils) on NSTX-U suggest the planned coils set is adequate for core and edge torque control. In conclusion, comparison between error field correction experiments on DIII-D and the optimizer show good agreement.},
doi = {10.1088/0741-3335/57/10/104001},
journal = {Plasma Physics and Controlled Fusion},
number = 10,
volume = 57,
place = {United States},
year = {Thu Sep 03 00:00:00 EDT 2015},
month = {Thu Sep 03 00:00:00 EDT 2015}
}
Web of Science
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Works referencing / citing this record:
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