Confinement and local transport in the National Spherical Torus Experiment (NSTX)
Creators
- 1. Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543 (United States)
- 2. Nova Photonics Inc., Princeton, NJ 08540 (United States)
- 3. The Johns Hopkins University, Baltimore, MD 21218 (United States)
- 4. University of California, Davis, CA 95616 (United States)
- 5. Institute for Fusion Studies, University of Texas, Austin, TX 78712 (United States)
- 6. Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
- 7. Department of Applied Physics, Columbia University, NYC, NY, 10027 (United States)
Description
The NSTX operates at low aspect ratio (R/a ∼ 1.3) and high beta (up to 40%), allowing tests of global confinement and local transport properties that have been established from higher aspect ratio devices. The NSTX plasmas are heated by up to 7 MW of deuterium neutral beams with preferential electron heating as expected for ITER. Confinement scaling studies indicate a strong BT dependence, with a current dependence that is weaker than that observed at higher aspect ratio. Dimensionless scaling experiments indicate a strong increase in confinement with decreasing collisionality and a weak degradation with beta. The increase in confinement with BT is due to reduced transport in the electron channel, while the improvement with plasma current is due to reduced transport in the ion channel related to the decrease in the neoclassical transport level. Improved electron confinement has been observed in plasmas with strong reversed magnetic shear, showing the existence of an electron internal transport barrier (eITB). The development of the eITB may be associated with a reduction in the growth of microtearing modes in the plasma core. Perturbative studies show that while L-mode plasmas with reversed magnetic shear and an eITB exhibit slow changes in LTe across the profile after the pellet injection, H-mode plasmas with a monotonic q-profile and no eITB show no change in this parameter after pellet injection, indicating the existence of a critical gradient that may be related to the q-profile. Both linear and non-linear simulations indicate the potential importance of electron temperature gradient (ETG) modes at the lowest BT. Localized measurements of high-k fluctuations exhibit a sharp decrease in signal amplitude levels across the L-H transition, associated with a decrease in both ion and electron transport, and a decrease in calculated linear microinstability growth rates across a wide k-range, from the ion temperature gradient/TEM regime up to the ETG regime
Additional details
Identifiers
- DOI
- 10.1088/0029-5515/47/7/001;
- PII
- S0029-5515(07)39645-2;
Publishing Information
- Journal Title
- Nuclear Fusion
- Journal Volume
- 47
- Journal Issue
- 7
- Journal Page Range
- p. 499-509
- ISSN
- 0029-5515
- CODEN
- NUFUAU
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38071364
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ASPECT RATIO; DEUTERIUM; ELECTRIC CURRENTS; ELECTRON TEMPERATURE; ELECTRONS; H-MODE PLASMA CONFINEMENT; HIGH-BETA PLASMA; ION TEMPERATURE; IONS; ITER TOKAMAK; L-MODE PLASMA CONFINEMENT; MAGNETIC FIELD CONFIGURATIONS; NEOCLASSICAL TRANSPORT THEORY; NONLINEAR PROBLEMS; NSTX DEVICE; PELLET INJECTION; RADIATION TRANSPORT; REVERSED SHEAR; TEMPERATURE GRADIENTS
- Descriptors DEC
- CHARGED PARTICLES; CHARGED-PARTICLE TRANSPORT THEORY; CLOSED PLASMA DEVICES; CONFINEMENT; CURRENTS; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; FERMIONS; HYDROGEN ISOTOPES; ISOTOPES; LEPTONS; LIGHT NUCLEI; MAGNETIC CONFINEMENT; NUCLEI; ODD-ODD NUCLEI; PLASMA; PLASMA CONFINEMENT; SPHEROMAK DEVICES; STABLE ISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSPORT THEORY