Transition from ITG to MTM linear instabilities near pedestals of high density plasmas

J. McClenaghan, T. Slendebroek, G. M. Staebler, S. P. Smith, O. M. Meneghini, B. A. Grierson, K. E. Thome, G. Avdeeva, L. L. Lao, J. Candy, W. Guttenfelder

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Abstract

Investigation of linear gyrokinetic ion-scale modes (k θ ρ s = 0.3) finds that a transition from ion temperature gradient to microtearing mode (MTM) dominance occurs as the density is increased near the pedestal region of a parameterized DIII-D sized tokamak. H-modes profile densities, temperatures, and equilibria are parameterized utilizing the OMFIT PRO_create module. With these profiles, linear gyrokinetic ion-scale instabilities are predicted with CGYRO. This transition (nMTM) has a weak dependence on radial location in the region near the top of the pedestal (ρ = 0.7 - 0.9), which allows simulating single radii to examine the approximate scaling of nMTM with global parameters. The critical nMTM is found to scale with plasma current. Additionally, increasing the minor radius by decreasing the aspect ratio and increasing the major radius are found to reduce nMTM. However, any relationship between nMTM and density limit physics remains unclear as nMTM increases relative to the Greenwald density with larger minor radius and with larger magnetic field, suggesting that the transport due to MTM may be less important for a reactor. Additionally, nMTM is sensitive to the pedestal temperature, the local electron and ion gradients, the ratio of ion to electron temperature T i / T e, and the current profile. MTMs are predicted to be the dominant instability in the core at similar Greenwald fractions for DIII-D, NSTX, and NSTX-U H-mode experiments, supporting the results of the parameterized study. Additionally, MTMs continue to be the dominant linear instability in a DIII-D L-mode after an H-L transition as the plasma approaches a density limit disruption despite the large change in plasma profiles.

Original languageEnglish
Article number042512
JournalPhysics of Plasmas
Volume30
Issue number4
DOIs
StatePublished - Apr 1 2023
Externally publishedYes

Funding

This material is based upon the 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 Award Nos. DE-FG02-95ER54309 (GA Theory Grant), DE-FC02-04ER54698 (DIII-D), DE-SC0021113, and DE-AC02-09CH11466. Part of the data analysis was performed using the OMFIT integrated modeling framework. Digital data for this paper can be found in http://arks.princeton.edu/ark:/88435/dsp018p58pg29j .

FundersFunder number
U.S. Department of Energy
Office of ScienceDE-AC02-09CH11466, DE-FC02-04ER54698, DE-FG02-95ER54309, DE-SC0021113
Fusion Energy Sciences

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