Fast scanning heterodyne receiver for the measurement of the time evolution of the electron temperature profile on the Tokamak Fusion Test Reactor

Taylor, G.; Efthimion, P. C.; McCarthy, Michael; Arunasalam, V.; Bitzer, R.; Bryer, J.; Cutler, R.; Fredd, E.; Goldman, M.; Kaufman, D.

doi:10.1063/1.1137668

Cited by 36 publications

(7 citation statements)

References 10 publications

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“…For the TRANSP modelling of this discharge, various combinations of inputs for the temperatures were investigated. For instance, the electron temperature T, was derived either from an absolutely calibrated, time dependent profile of first harmonic ECE measured by a radiometer [15] or from the time dependent profile of second harmonic ECE measured by a grating polychromator (GPC) [16]. In the latter case, the profile was cross-calibrated either by the second harmonic ent TRANSP runs.…”

Section: Transp Modelling Of Supershot 55851mentioning

confidence: 99%

Simulations of deuterium-tritium experiments in TFTR

Budny¹,

Bell²,

Biglari³

et al. 1992

Nucl. Fusion

175

105

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A transport code (TRANSP) is used to simulate future deuterium-tritium (DT) experiments in TFTR. The simulations are derived from 14 TFTR DD discharges, and the modelling of one supershot is discussed in detail to indicate the degree of accuracy of the TRANSP modelling. Fusion energy yields and 01 particle parameters are calculated, including profiles of the 01 slowing down time, the 01 average energy, and the AlfvBn speed and frequency. Two types of simulation are discussed. The main emphasis is on the DT equivalent, where an equal mix of D and T is substituted for the D in the initial target plasma, and for the Do in the neutral beam injection, but the other measured beam and plasma parameters are unchanged. This simulation does not assume that 01 heating will enhance the plasma parameters or that confinement will increase with the addition of tritium. The maximum relative fusion yield calculated for these simulations is QDT-0.3, and the maximum a contribution to the central toroidal 0 is PJO)-0.5%. The stability of toroidicity induced Alfvkn eigenmodes (TAE) and kinetic ballooning modes (KBM) is discussed. The TAE mode is predicted to become unstable for some of the simulations, particularly after the termination of neutral beam injection. In the second type of simulation, empirical supershot scaling relations are used to project the performance at the maximum expected beam power. The MHD stability of the simulations is discussed.

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Section: Transp Modelling Of Supershot 55851mentioning

confidence: 99%

Simulations of deuterium-tritium experiments in TFTR

Budny¹,

Bell²,

Biglari³

et al. 1992

Nucl. Fusion

175

105

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“…So far, methods (1) and ( 2) have yielded j(r) profile measurements to about 15% accuracy at the plasma centre, but the accuracy is rather poor near the edge. However, fairly precise measurements of T e (r) profiles are available via (1) laser Thomson scattering [49], (2) black-body electron cyclotron emission [50][51][52], and (3) soft X-ray energy spectrum measurements along radial chords and subsequent Abel inversion [53]. Hence, in this paper we will take the T e (r) profile and not the j(r) profile as the only reasonably precisely measurable profile at the present time.…”

Section: Outline Of the Analytical Proceduresmentioning

confidence: 99%

Self-consistency of the principle of profile consistency results for sawtoothing tokamak discharges

et al. 1990

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DISCLAIMERThis i-eport was prepared as an accouni of +ork sponsored hy an agency uf the United States Government Neither (he United Slates Government nor jn> agency thereof, nor any of their employees, makes any warranty, express or implied. 01 assume* any legal liability or responsihilili for the accuracy, completeness, or usefulness af any infocmauon, apparatus, product. 01 process disclosed, or represents that its use would not infringe privately owned rights Refer ence herein to any specific commercial product, process, or service hy trade name, trademark, manufacturer, or otherwise docs (tot necessarily constitute or imply its endorsement, recom mendation, or favoring by the United States Government or any agency thereof The views and opinions of authors expressed herein do not necessarily state ur reflect those of the Vimlcd States Government or any agency (hereof •AT&T Microelectronics, Reading, PA 19612 **0ak Ridge National Laboratory, Oak Ridge, TN 37831 if \S 2 ABSTRACT The principle of profile consistency states that for fixed limiter safety factor q,, there exists unique natural equilibrium profile shapes for the a. current density j(r) [and consequently q(r)], and the electron temperature T (r) for any tokamak plasma independent of the shapes of the heating power deposition profiles. The mathematical statement of the three basic consequences of this principle for sawtoothing discharges [i.e., discharges with q(0) < 1) are: (1) (r^a) = F, M/q a > [= Vq a , empirically], (2) /T"" = F 5 (1/q_), and (3) a unique scaling law for the central electron S SO tl d temperature T , where r 1 is the sawtooth inversion radius [i.e., q(r^) = 1] and is the volume average T . Since for a given T (r), the ohmic current J(r) can be deduced from Ohm'3 law, given the function F^, the function F 2 is uniquely fixed and vice versa. Also given F^(Vq_), the central current density J Q = (V L /2nbRZ eff ) T|^2 = (I /*a 2 ) Fg(q a ), where the function F3 = (q a /q Q ) is uniquely fixed by F^ Here b = 6.53 * 10^ unA, and I , V L> Z ff >, R, a, and q are the plasma current, loop voltage, effective ion charge, major and minor radius, and the central safety factor, respectively. Thus for a fixed J(r) or T (r), the set of functions F^ F 2 , and F-, is uniquely fixed. Further, the principle of profile consistency [i.e., the existence of unique natural equilibrium profile shapes far J(r) and T e

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“…The ion temperatures for these discharges were measured by the TFTR Group with charge exchange recombination spectroscopy ͑CHERS͒; 18 the electron density profiles were obtained with the multichannel infrared interferometer ͑MIRI͒ diagnostic; 19 and the electron temperatures were measured with electron cyclotron emission ͑ECE͒. 20 The CHERS diagnostic technique provides the error bars on the ion temperature points. Fractional errors for ECE electron temperature data typically range from 5% to 10%; our standard procedure is to assume fractional error bars of 7.5%.…”

Section: B Experimental Profilesmentioning

confidence: 99%

Predictive simulations of tokamak plasmas with a model for ion-temperature-gradient-driven turbulence

et al. 1998

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A drift wave transport model, recently developed by Ottaviani, Horton and Erba ͑OHE͒ ͓Ottaviani et al., Plasma Phys. Controlled Fusion 39, 1461 ͑1997͔͒, has been implemented and tested in a time-dependent predictive transport code. This OHE model assumes that anomalous transport is due to turbulence driven by ion temperature gradients and that the fully developed turbulence will extend into linearly stable regions, as described in the reference cited above. A multiplicative elongation factor is introduced in the OHE model and simulations are carried out for 12 discharges from major tokamak experiments, including both L-and H-modes ͑lowand high-confinement modes͒ and both circular and elongated discharges. Good agreement is found between the OHE model predictions and experiment. This OHE model is also used to describe the performance of the International Thermonuclear Experimental Reactor ͑ITER͒ ͓Putvinski et al., in 737.͔ A second version of the OHE model, in which the turbulent transport is not allowed to penetrate into linearly stable regions, has also been implemented and tested. In simulations utilizing this version of the model, the linear stability of the plasma core eliminates the anomalous thermal transport near the magnetic axis, resulting in an increase in the core temperatures to well above the experimental values.

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Fast scanning heterodyne receiver for the measurement of the time evolution of the electron temperature profile on the Tokamak Fusion Test Reactor

Cited by 36 publications

References 10 publications

Simulations of deuterium-tritium experiments in TFTR

Simulations of deuterium-tritium experiments in TFTR

Self-consistency of the principle of profile consistency results for sawtoothing tokamak discharges

Predictive simulations of tokamak plasmas with a model for ion-temperature-gradient-driven turbulence

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