1998
DOI: 10.1088/0029-5515/38/11/301
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Plasma exhaust and density control in tokamak fusion experiments with neutral beam or ICRF auxiliary heating

Abstract: Particle exhaust studies have been carried out with the pump limiter ALT-II in the TEXTOR tokamak, under ohmic conditions as well as with NBI and with ICRF auxiliary heating, and the pumping effectiveness is shown to meet the requirements for a fusion reactor. Quantitative measurements of Dα emission, made with a CCD camera, have been used to determine the particle efflux from the plasma. Roughly one third of the Dα emission occurs in a diffuse `halo' that surrounds the limiter belt. The particle confinem… Show more

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Cited by 17 publications
(10 citation statements)
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“…The main reciprocating probe is located at the outer midplane of the tokamak and the second probe is at the top. TEXTOR edge plasmas are toroidally symmetric due to the ALT-II belt limiter [21]. The data for the turbulent measurements are digitized at 1 MHz with a 10 bit digitizer and filtered by low pass 500 kHz anti-aliasing filters.…”
Section: Description Of Experimentsmentioning
confidence: 99%
“…The main reciprocating probe is located at the outer midplane of the tokamak and the second probe is at the top. TEXTOR edge plasmas are toroidally symmetric due to the ALT-II belt limiter [21]. The data for the turbulent measurements are digitized at 1 MHz with a 10 bit digitizer and filtered by low pass 500 kHz anti-aliasing filters.…”
Section: Description Of Experimentsmentioning
confidence: 99%
“…The H α emission in TEXTOR during polarization has been analysed with a calibrated CCD camera [41] observing the ALT-II limiter. The camera signal is integrated over a large area, including an entire limiter blade and parts of the wall, to increase the signal to noise ratio and to account for the contribution of extended poloidal 'halos', which have been shown to contain about 50% of the signal in low plasma density discharges such as these.…”
Section: Particle and Energy Confinementmentioning
confidence: 99%
“…For this purpose, two systems have been developed to manage the plasma-wall interaction, namely limiters and divertors. Whereas limiters have demonstrated extensively their ability to control the density [1][2][3][4][5] they suffer from the presence of a leading edge, upon which the heat load can reach intolerable values during high power discharges and from an insufficient decoupling between the plasma core and the edge, which can lead to significant impurity penetration. This decoupling is achieved with axisymmetric poloidal divertors and has led to good results in terms of confinement, impurity screening and power deposition [6].…”
Section: Introductionmentioning
confidence: 99%