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  • 11
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 58 (1987), S. 12-16 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: A specialized method has been developed to maximize the two-dimensional detail obtained from two perpendicular bolometer arrays. The technique relies on the assumption that poloidal variation exists only near the plasma surface. The cross section is divided into appropriate zones and the emittance is reconstructed by a numerical method. The position, intensity, and width of large features are clearly displayed. A marfe is tracked as it drifts around the plasma and evolves into a radiating shell detached from the limiter. A central peak, plus inner-wall radiating layer, plus a marfe appear in a high-density case reached by pellet injection.
    Type of Medium: Electronic Resource
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  • 12
    ISSN: 1089-7666
    Source: AIP Digital Archive
    Topics: Physics
    Notes: General plasma physics principles state that power flow Q(r) through a magnetic surface in a tokamak should scale as Q(r)= {32π2Rr3Te2c nea/[eB (a2−r2)2]} F(ρ*,β,ν*,r/a,q,s,r/R,...) where the arguments of F are local, nondimensional plasma parameters and nondimensional gradients. This paper reports an experimental determination of how F varies with normalized gyroradius ρ*≡(2TeMi)1/2c/eBa and collisionality ν*≡(R/r)3/2qRνe(me/ 2Te)1/2 for discharges prepared so that other nondimensional parameters remain close to constant. Tokamak Fusion Test Reactor (TFTR) [D. M. Meade et al., in Plasma Physics and Controlled Nuclear Fusion Research, 1990, Proceedings of the 13th International Conference, Washington (International Atomic Energy Agency, Vienna, 1991), Vol. 1, p. 9] L-mode data show F to be independent of ρ* and numerically small, corresponding to Bohm scaling with a small multiplicative constant. By contrast, most theories predict gyro-Bohm scaling: F∝ρ*. Bohm scaling implies that the largest scale size for microinstability turbulence depends on machine size. Analysis of a collisionality scan finds Bohm-normalized power flow to be independent of collisionality. Implications for future theory, experiment, and reactor extrapolations are discussed.
    Type of Medium: Electronic Resource
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  • 13
    ISSN: 1089-7666
    Source: AIP Digital Archive
    Topics: Physics
    Notes: Using perturbations in electron density and temperature induced by small helium gas puffs in TFTR (Tokamak Fusion Test Reactor) [Plasma Phys. Controlled Nucl. Fusion Res. 1, 51 (1986)], the dominance of convective heat transport in the core (r/a〈0.4) of supershot plasmas has been demonstrated in a new way. The transp [J. Comput. Phys. 43, 61 (1981)] transport code was used to calculate the time-dependent particle and heat fluxes. Perturbations in the calculated convective and total electron heat fluxes were compared. They demonstrate that the conductive component decreases moving into the supershot core, and the convective component dominates in the supershot core. These results suggest a different transport drive in the supershot core compared to that in the rest of the supershot plasma.
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  • 14
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Circular limiter H modes with centrally peaked density profiles have been obtained on TFTR. Diagnostics used to study these unique plasmas include arrays of Dα and C ii detectors, bolometers, and Mirnov coils; x-ray imaging, charge exchange recombination spectroscopy, ECE, microwave scattering systems, and a multichannel infrared interferometer. These diagnostics have special features which allow time and space-resolved measurements during the H-mode transition and during ELMs. Microwave scattering during the H phase shows a feature in the scattered spectrum which is consistent with a poloidal rotation in the electron diamagnetic drift direction. Mirnov coil data digitized at 2 MHz show an increase in high-frequency magnetic fluctuations (60–200 kHz) during an ELM, while ECE data show 20–30 μs intense emission spikes in the outer 15–20 cm of the plasma edge.
    Type of Medium: Electronic Resource
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  • 15
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Circular limiter H modes with centrally peaked density profiles have been obtained on TFTR. Diagnostics used to study these unique plasmas include arrays of Dα and C ii detectors, bolometers, and Mirnov coils; x-ray imaging, charge exchange recombination spectroscopy, ECE, microwave scattering systems, and a multichannel infrared interferometer. These diagnostics have special features which allow time and space-resolved measurements during the H-mode transition and during ELMs. Microwave scattering during the H phase shows a feature in the scattered spectrum which is consistent with a poloidal rotation in the electron diamagnetic drift direction. Mirnov coil data digitized at 2 MHz show an increase in high-frequency magnetic fluctuations (60–200 kHz) during an ELM, while ECE data show 20–30 μs intense emission spikes in the outer 15–20 cm of the plasma edge.
    Type of Medium: Electronic Resource
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  • 16
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 63 (1992), S. 4760-4762 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: We have developed a code for following the radial diffusion and slowing down of alpha particles from DT fusion. The partial differential equation is solved by a finite-difference method. Ion as well as electron drag is included. Any given source function of radius, time, and energy width can be handled correctly. The code has been used to examine time waveforms, radial distributions, and energy spectra. The results can be used to model signals expected from the alpha charge exchange recombination spectroscopy and collective Thomson ("gyrotron'') scattering diagnostics. The code has also been used to calculate, as a function of diffusion coefficient, the flux of escaping fast ions that enters a lost-ion detector, and thus to deduce from measurements an upper limit for the diffusion of fast charged fusion products.
    Type of Medium: Electronic Resource
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  • 17
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 57 (1986), S. 2081-2083 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: The profiles are measured in the tokamak fusion test reactor (TFTR) with two bolometer arrays, one of which looks in at the plasma horizontally and one vertically. Under some conditions the profiles have large, localized features. The most common are a bright band of radiation near the inner wall (usually referred to as a "marfe'') and a wide bright layer that occurs when the plasma is in contact with the inner bumper limiter. The asymmetric profiles have been analyzed in three ways: by inspection, by separating the excess over the normal part of the profile, and by a 2-D reconstruction procedure in which the cross section is divided into zones tailored to our specific geometry. Inspection shows the motion of the bright band and its development into a bright shell. Integration of the excess yields the power in the band. This power rises smoothly and dramatically as a function of density as one nears the high-density limit. However, it needs to be taken into account in profile Abel inversion even at modest densities. The 2-D reconstruction yields, among other results, the intensity and the thickness of the inner-bumper layer. These are typically 300 kW/m3 and approximately 0.1 m. The reconstruction is not accurate enough to be used as a substitute for Abel inversion.
    Type of Medium: Electronic Resource
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  • 18
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 57 (1986), S. 2078-2080 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Bolometers located at a number of toroidal and poloidal positions are used to determine the toroidal distribution of impurity radiation losses from the Tokamak Fusion Test Reactor (TFTR) plasmas. Distributions for both OH and beam-heated D+ and He++ plasmas have been determined. The distributions are highly peaked at the limiter sector for plasmas run on the outer limiter but more symmetric toroidally when run on the inner bumper limiter. Plasmas detached from both inner and outer limiters have distributions which are basically symmetric toroidally and poloidally. The widths of toroidally peaked distributions are ≤1 sector of the 20 sector torus. Scalings of the enhanced radiative losses at the limiter with input power are indicated.
    Type of Medium: Electronic Resource
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  • 19
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 56 (1985), S. 972-974 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: For the past year we have been making use of a horizontally viewing 19-channel array and a bolometer which views a narrow cross-sectional slice of the plasma. More recently, we have also obtained results from a second, vertically viewing array. Software has been developed to translate the data from general plasma and array locations to plasma minor radius and to do the Abel inversion with an antisymmetrical term included. Experience has been obtained on the noise and response-time characteristics, as well as the accuracy of total radiated power and radial profiles. Representative cases of radiated power profiles and local power balance are presented, as well as comparisons with other measurements of impurity concentration and trends with electron density and limiter coating. Although most of the ohmic-heating input power leaves by radiation, most of this loss occurs near the outer part of the plasma. Also, the behavior of power profiles during neutral beam injection is discussed briefly.
    Type of Medium: Electronic Resource
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  • 20
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 56 (1985), S. 849-851 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Soft-x-ray (5–300 A(ring)) spectra of intrinsic impurities have been recorded with a high-resolution multichannel XUV spectrometer (SOXMOS). Measurements of line intensity ratios as a function of time are applied to the determination of the impurity contribution to the energy balance. Results from TFTR Ohmic heated plasmas, including radiation due to carbon, oxygen, iron, nickel, chromium, titanium, and zirconium, are presented. The spatial ion distribution will be directly observed by a radial scanning spectrometer (FLOPSY). This instrument, under construction, will cover the spectral range from 1500 to 7000 A(ring) and use mirrors and lenses for fast scanning. The spatial ion distribution, deduced from forbidden and allowed lines, will be compared to both theoretical models based on impurity concentrations and transport coefficients, as well as experimental data from bolometer measurements.
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