Helium transport and exhaust studies in enhanced confinement regimes in DIII-D

Wade, M. R.; Hillis, D.L.; Hogan, J.; Maingi, R.; Menon, M. M.; Mahdavi, M. A.; West, W.P.; Burrell, K.H.; Gohil, P.; Groebner, R. J.; Rao, Hong; Kellman, D.H.; Phillips, J. C.; Seraydarian, R.; Finkenthal, D. F.

doi:10.1063/1.871489

Cited by 79 publications

(76 citation statements)

References 15 publications

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“…The electron density (ne) profile is measured using multi-pulse Thomson scattering [29] The ion temperature (Ti) profile is determined from charge exchange recombination (CER) emission of carbon impurities [31]. The carbon density found from the CER emission also determines the average ion charge (ZeR) profile [32]. An array of foil bolometers is used to measure the radiated power (Prad) profile [33].…”

Section: Methodsmentioning

confidence: 99%

Safety factor scaling of energy transport in L-mode plasmas on the DIII-D tokamak

2004

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The scaling of energy transport with safety factor (q) at fixed magnetic shear has been measured on the DIII-D tokamak [Nucl. Fusion 42, 614 (2002)l for low confinement (L) mode discharges. At constant density, temperature, and toroidal magnetic field strength, such that the toroidal dimensionless parameters other than q are held fixed, the one-fluid thermal diffusivity is found to scale like X 0~ q0.84+0.15, with the ion channel having a stronger q dependence than the electron channel in the outer half of the plasma. The measured q scaling is in good agreement with the predicted scaling by the GLF23 transport model for the ion temperature gradient and trapped electron modes, but it is significantly weaker than the inferred scaling from empirically-derived confinement scaling relations.... 111

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Section: Methodsmentioning

confidence: 99%

Safety factor scaling of energy transport in L-mode plasmas on the DIII-D tokamak

2004

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“…This formula is seldom used for the evaluation of the transport coefficients because of the difficulty in measuring the total impurity ion density experimentally. Previous applications to impurity transport [14] used charge exchange recombination spectroscopy (CXRS) while in a recent work [15] the method has been applied to study electron transport in-between sawtooth crashes within the q = 1 surface. Other impurity transport studies (e.g.…”

Section: Determination Of the Impurity Transport Coefficientsmentioning

confidence: 99%

Local effects of ECRH on argon transport in L-mode discharges at ASDEX Upgrade

Sertoli

Angioni

Dux

et al. 2011

Plasma Phys. Control. Fusion

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Abstract. The transport of argon as trace impurity has been investigated in electron cyclotron resonance heated L-mode discharges at ASDEX Upgrade to test recent theories predicting the rise of an outward impurity convection. The profiles of the argon transport coefficients for r/a < 0.65 have been determined by analysing the linear flux-gradient dependency of the total argon ion density evolution after the puff. A new methodology to experimentally obtain the total impurity ion density from the integrated use of two spectroscopic diagnostic and the 1D impurity transport code STRAHL has been developed. Results confirm the enhancement in diffusivity and the rise of the positive convection observed in previous studies, but show for the first time how these effects are strongly localized around the electron cyclotron resonance heating deposition radius. These experimental results are found in promising qualitative agreement with a set of quasi-linear gyrokinetic simulations with the code GS2.

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“…This allows determination of E r in the plasma core and understanding of its evolution when transport barriers develop [27,28]. In addition, helium transport studies based on this analysis demonstrated that helium exhaust in ELMing H-mode plasmas is sufficiently fast for helium ash removal in tokamak fusion reactors [32,33].…”

Section: A Charge Exchange Recombinationmentioning

confidence: 99%

DIII-D Diagnostic Systems

Boivin¹,

Luxon²,

Austin

et al. 2005

Fusion Science and Technology

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The DIII-D tokamak, located at General Atomics in San Diego, California, has long been recognized as being one of the best diagnosed magnetic fusion experiments.Composed of more than 50 individual systems, the diagnostic set takes advantage of a high number of large aperture access ports. These instruments are used in support of basic control of the tokamak and experiments in the transport, stability, boundary and heating and current drive science areas. These systems have contributed to the success of the Advanced Tokamak (AT) program, in addition to the many contributions to our physics understanding and real-time control of fusion-relevant plasmas. Numerous novel techniques have been developed, tested, and fielded on DIII-D including new approaches required for a Burning Plasma Experiment (BPX). Details of the diagnostic systems will be described along with some illustrative recent results.

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Helium transport and exhaust studies in enhanced confinement regimes in DIII-D

Abstract: Portions of this document may be illegible in electronic image products. lmages are produced from the best available original document.

Cited by 79 publications

References 15 publications

Safety factor scaling of energy transport in L-mode plasmas on the DIII-D tokamak

Safety factor scaling of energy transport in L-mode plasmas on the DIII-D tokamak

Local effects of ECRH on argon transport in L-mode discharges at ASDEX Upgrade

DIII-D Diagnostic Systems

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