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Stabilizing effect of resistivity towards ELM-free H-mode discharge in lithium-conditioned NSTX

Journal Article · · Nuclear Fusion
 [1];  [2];  [3]
  1. Univ. of Science and Technology of China, Hefei (China). CAS Key Lab. of Geospace Environment and Dept. of Modern Physics
  2. Univ. of Science and Technology of China, Hefei (China). CAS Key Lab. of Geospace Environment and Dept. of Modern Physics; Univ. of Wisconsin, Madison, WI (United States). Dept. of Engineerng Physics
  3. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Linear stability analysis of the national spherical torus experiment (NSTX) Li-conditioned ELM-free H-mode equilibria is carried out in the context of the extended magneto-hydrodynamic (MHD) model in NIMROD. Our purpose is to investigate the physical cause behind edge localized mode (ELM) suppression in experiment after the Li-coating of the divertor and the first wall of the NSTX tokamak. Besides ideal MHD modeling, including finite-Larmor radius effect and two-fluid Hall and electron diamagnetic drift contributions, a non-ideal resistivity model is employed, taking into account the increase of Z eff after Li-conditioning in ELM-free H-mode. And unlike an earlier conclusion from an eigenvalue code analysis of these equilibria, NIMROD results find that after reduced recycling from divertor plates, profile modification is necessary but insufficient to explain the mechanism behind complete ELMs suppression in ideal two-fluid MHD. After considering the higher plasma resistivity due to higher Z eff, the complete stabilization could be explained. Furthermore, a thorough analysis of both pre-lithium ELMy and with-lithium ELM-free cases using ideal and non-ideal MHD models is presented, after accurately including a vacuum-like cold halo region in NIMROD to investigate ELMs.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Grant/Contract Number:
FG02-86ER53218; FC02-08ER54975; AC02-05CH11231; AC02-09CH11466
OSTI ID:
1360935
Alternate ID(s):
OSTI ID: 22925772
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 7 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (26)

Nonlinear magnetohydrodynamics simulation using high-order finite elements journal March 2004
Analysis of a mixed semi-implicit/implicit algorithm for low-frequency two-fluid plasma modeling journal August 2010
Edge localized linear ideal magnetohydrodynamic instability studies in an extended-magnetohydrodynamic code journal March 2010
Ideal and resistive edge stability calculations with M3D-C1 journal October 2010
Edge transport and turbulence reduction with lithium coated plasma facing components in the National Spherical Torus Experiment journal May 2011
The impact of collisionality, FLR, and parallel closure effects on instabilities in the tokamak pedestal: Numerical studies with the NIMROD code journal June 2016
Stabilizing effects of enhanced resistivity due to lithium-conditioning on low- n edge localized modes in NSTX journal May 2017
The general “peeling” instability journal February 1975
Observation of a high performance operating regime with small edge-localized modes in the National Spherical Torus Experiment journal March 2005
H-mode pedestal, ELM and power threshold studies in NSTX journal August 2005
Chapter 4: Power and particle control journal June 2007
Stability and dynamics of the edge pedestal in the low collisionality regime: physics mechanisms for steady-state ELM-free operation journal August 2007
ITER predictions using the GYRO verified and experimentally validated trapped gyro-Landau fluid transport model journal June 2011
The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment journal June 2012
Edge microstability of NSTX plasmas without and with lithium-coated plasma-facing components journal September 2013
Core transport of lithium and carbon in ELM-free discharges with lithium wall conditioning in NSTX journal July 2013
Enhanced H-mode pedestals with lithium injection in DIII-D journal May 2015
High frequency pacing of edge localized modes by injection of lithium granules in DIII-D H-mode discharges journal April 2016
Stability of toroidal plasmas: the influence of magnetic shear, periodicity and rotation journal November 2004
Characterization of peeling–ballooning stability limits on the pedestal journal April 2004
The relationships between edge localized modes suppression, pedestal profiles and lithium wall coatings in NSTX journal September 2011
Edge-Localized-Mode Suppression through Density-Profile Modification with Lithium-Wall Coatings in the National Spherical Torus Experiment journal August 2009
Triggered Confinement Enhancement and Pedestal Expansion in High-Confinement-Mode Discharges in the National Spherical Torus Experiment journal September 2010
Plasmoid Formation in Current Sheet with Finite Normal Magnetic Component journal June 2013
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak journal February 2015
Plasmoids Formation During Simulations of Coaxial Helicity Injection in the National Spherical Torus Experiment journal May 2015

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