Gyrokinetic Stability Studies of the Microtearing Mode in the National Spherical Torus Experiment H-mode

Technical Report · Wed Oct 19 04:00:00 EDT 2005

DOI:https://doi.org/10.2172/899586· OSTI ID:899586

Baumgaertel, J. A.; Redi, M. H.; Budny, R. V.; Rewoldt, G.; Dorland, W.

Insight into plasma microturbulence and transport is being sought using linear simulations of drift waves on the National Spherical Torus Experiment (NSTX), following a study of drift wave modes on the Alcator C-Mod Tokamak. Microturbulence is likely generated by instabilities of drift waves, which cause transport of heat and particles. Understanding this transport is important because the containment of heat and particles is required for the achievement of practical nuclear fusion. Microtearing modes may cause high heat transport through high electron thermal conductivity. It is hoped that microtearing will be stable along with good electron transport in the proposed low collisionality International Thermonuclear Experimental Reactor (ITER). Stability of the microtearing mode is investigated for conditions at mid-radius in a high density NSTX high performance (H-mode) plasma, which is compared to the proposed ITER plasmas. The microtearing mode is driven by the electron temperature gradient, and believed to be mediated by ion collisions and magnetic shear. Calculations are based on input files produced by TRXPL following TRANSP (a time-dependent transport analysis code) analysis. The variability of unstable mode growth rates is examined as a function of ion and electron collisionalities using the parallel gyrokinetic computational code GS2. Results show the microtearing mode stability dependence for a range of plasma collisionalities. Computation verifies analytic predictions that higher collisionalities than in the NSTX experiment increase microtearing instability growth rates, but that the modes are stabilized at the highest values. There is a transition of the dominant mode in the collisionality scan to ion temperature gradient character at both high and low collisionalities. The calculations suggest that plasma electron thermal confinement may be greatly improved in the low-collisionality ITER.

• Research Organization: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
• Sponsoring Organization: USDOE - Office of Science (SC)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 899586
• Report Number(s): PPPL-4119
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CONFINEMENT
CONTAINMENT
ELECTRON TEMPERATURE
ELECTRONS
EXPERIMENTAL REACTORS
INSTABILITY GROWTH RATES
ION COLLISIONS
ION TEMPERATURE
Microturbulence
PERFORMANCE
PHYSICS
PLASMA
SHEAR
STABILITY
THERMAL CONDUCTIVITY
TRANSPORT
microtearing growth
plasma collisionalities