Title
Use of reconstructed 3D equilibria to determine onset conditions of helical cores in tokamaks for extrapolation to ITER
Date Issued
15 January 2018
Access level
metadata only access
Resource Type
journal article
Author(s)
Wingen A.
Wilcox R.
Seal S.
Unterberg E.
Cianciosa M.
Hirshman S.
Lao L.
Princeton University
Publisher(s)
Institute of Physics Publishing
Abstract
Large, spontaneous m/n = 1/1 helical cores are shown to be expected in tokamaks such as ITER with extended regions of low- or reversed- magnetic shear profiles and q near 1 in the core. The threshold for this spontaneous symmetry breaking is determined using VMEC scans, beginning with reconstructed 3D equilibria from DIII-D and Alcator C-Mod based on observed internal 3D deformations. The helical core is a saturated internal kink mode (Wesson 1986 Plasma Phys. Control. Fusion 28 243); its onset threshold is shown to be proportional to around q = 1. Below the threshold, applied 3D fields can drive a helical core to finite size, as in DIII-D. The helical core size thereby depends on the magnitude of the applied perturbation. Above it, a small, random 3D kick causes a bifurcation from axisymmetry and excites a spontaneous helical core, which is independent of the kick size. Systematic scans of the q-profile show that the onset threshold is very sensitive to the q-shear in the core. Helical cores occur frequently in Alcator C-Mod during ramp-up when slow current penetration results in a reversed shear q-profile, which is favorable for helical core formation. Finally, a comparison of the helical core onset threshold for discharges from DIII-D, Alcator C-Mod and ITER confirms that while DIII-D is marginally stable, Alcator C-Mod and especially ITER are highly susceptible to helical core formation without being driven by an externally applied 3D magnetic field.
Volume
58
Issue
3
Language
English
OCDE Knowledge area
Física de plasmas y fluídos
Física nuclear
Subjects
Scopus EID
2-s2.0-85042150135
Source
Nuclear Fusion
ISSN of the container
00295515
Sponsor(s)
Discussions with A. Turnbull, Robert Granetz, Syunichi Shiraiwa and Amanda Hubbard are gratefully acknowledged. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility under awards, DE-AC05-00OR22725, DE-AC02-09CH11466 and DE-FC02-04ER54698. DIII-D data shown in this paper can be obtained in digital format by following the links at https://fusion.gat. com/global.D3D_DMP. This work used resources of the Oak Ridge Leadership Computing Facility.
Sources of information:
Directorio de Producción Científica
Scopus