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Title: Numerical optimization of three-dimensional coils for NSTX-U

Journal Article · · Plasma Physics and Controlled Fusion

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.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1255635
Alternate ID(s):
OSTI ID: 1238861
Report Number(s):
PPPL-5181
Journal Information:
Plasma Physics and Controlled Fusion, Vol. 57, Issue 10; ISSN 0741-3335
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 6 works
Citation information provided by
Web of Science

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Cited By (2)

Mitigation of Alfvénic activity by 3D magnetic perturbations on NSTX journal July 2016
Magnetic polarization measurements of the multi-modal plasma response to 3D fields in the EAST tokamak journal May 2018