Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Error field impact on mode locking and divertor heat flux in NSTX-U

Journal Article · · Nuclear Fusion
During the 2016 NSTX-U experimental campaign, locked modes in the plasma edge presented clear evidence of the presence of error fields. Extensive metrology and plasma response modeling with IPEC and M3D-C1 have been conducted to understand the various sources of error fields in NSTX-U as built in 2016, and to determine which of these sources have the greatest effect on the plasma. In particular, modeling finds that the error field from misalignment of the toroidal field (TF) coils may have a significant effect on the plasma. The response to the TF error field is shown to depend on the presence of a q = 1 surface, in qualitative agreement with experimental observations. It is found that certain characteristics of the TF error field present new challenges for error field correction. Specifically, the error field spectrum differs significantly from that of coils on the low-field side (such as the NSTX-U error field correction coils), and does not resonate strongly with the dominant kink mode, thus potentially requiring a multi-mode correction. Moreover, to mitigate heat fluxes using poloidal flux expansion, the pitch angle at the divertor plates must be small (~1°). It is shown that uncorrected error fields may result in potentially significant local perturbation to the pitch angle. Estimates for coil alignment tolerances in NSTX-U are derived based on consideration of both heat flux and core resonant fields independently.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24); USDOE Office of Science (SC), Fusion Energy Sciences (FES)(SC-24)
Grant/Contract Number:
AC02-09CH11466; AC04-94AL85000; AC05-00OR22725; FC02-04ER54698; SC0012706
OSTI ID:
1529148
Alternate ID(s):
OSTI ID: 1532736
OSTI ID: 22808023
OSTI ID: 1594315
OSTI ID: 22929849
Report Number(s):
SAND--2019-2558J; 673251
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 8 Vol. 59; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (26)

A method to measure poloidal field coil irregularities in toroidal plasma devices journal September 1991
Modeling of active control of external magnetohydrodynamic instabilities journal May 2001
Magnetohydrodynamic-activity-induced toroidal momentum dissipation in collisionless regimes in tokamaks journal May 2003
Nonaxisymmetric field effects on Alcator C-Mod journal May 2005
Computation of three-dimensional tokamak and spherical torus equilibria journal May 2007
Neoclassical toroidal viscosity and error-field penetration in tokamaks journal May 2008
Spectral asymmetry due to magnetic coordinates journal June 2008
Calculations of two-fluid linear response to non-axisymmetric fields in tokamaks journal May 2012
Self-consistent perturbed equilibrium with neoclassical toroidal torque in tokamaks journal March 2017
Mode locking in tokamaks journal December 1990
Effect of resonant magnetic perturbations on COMPASS-C tokamak discharges journal December 1992
Interaction of tearing modes with external structures in cylindrical geometry (plasma) journal July 1993
Error field mode studies on JET, COMPASS-D and DIII-D, and implications for ITER journal November 1999
Error field experiments in JET journal April 2000
Multi-mode error field correction on the DIII-D tokamak journal March 2003
 -Limiting MHD instabilities in improved-performance NSTX spherical torus plasmas journal April 2003
Investigation of resistive wall mode stabilization physics in high-beta plasmas using applied non-axisymmetric fields in NSTX journal August 2007
Study of in-vessel nonaxisymmetric ELM suppression coil concepts for ITER journal January 2008
Resonant magnetic perturbation experiments on MAST using external and internal coils for ELM control journal February 2010
Overview of the physics and engineering design of NSTX upgrade journal July 2012
The spectral basis of optimal error field correction on DIII-D journal April 2014
Overview of NSTX Upgrade initial results and modelling highlights journal June 2017
Scenario development during commissioning operations on the National Spherical Torus Experiment Upgrade journal February 2018
Error Field Amplification and Rotation Damping in Tokamak Plasmas journal May 2001
Suppression of Large Edge-Localized Modes in High-Confinement DIII-D Plasmas with a Stochastic Magnetic Boundary journal June 2004
Active Control of Type-I Edge-Localized Modes with n = 1 Perturbation Fields in the JET Tokamak journal June 2007