TEXTOR: A Pioneering Device for New Concepts in Plasma-Wall Interaction, Exhaust, and Confinement

Samm, U.

doi:10.13182/fst05-a688

Cited by 33 publications

(28 citation statements)

References 26 publications

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“…Several systems are being developed to detect and control such modes. On the tokamak experiment for technology oriented research (TEXTOR: major radius R = 1.75 m, minor radius a = 0.46 m), 3 a feedback system has successfully demonstrated the suppression of tearing modes using microwaves. 4 However, in specific electron density intervals, the system recorded large unexplained perturbations which could hamper the proper working of the feedback loop.…”

Section: Introductionmentioning

confidence: 99%

Modification of the collective Thomson scattering radiometer in the search for parametric decay on TEXTOR

Nielsen

Salewski

Bongers

et al. 2012

Review of Scientific Instruments

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Section: Introductionmentioning

confidence: 99%

Modification of the collective Thomson scattering radiometer in the search for parametric decay on TEXTOR

Nielsen

Salewski

Bongers

et al. 2012

Review of Scientific Instruments

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“…TEXTOR is a medium size tokamak (major radius 1.75 m, minor radius 0.46 cm) with a circular poloidal plasma cross-section [1]. The position of the last closed flux surface (LCFS) is defined by the toroidal belt limiter ALT-II (Advanced Limiter Test II) [2].…”

Section: Introductionmentioning

confidence: 99%

“…1 (a,b)). The original tiles [3] first installed in 1987 1 have a shape with a tangential geometry (angle of incidence of the magnetic field α of ~ 0.1°) for the central 2/3 of the poloidal range of the blade. The edges curve away with α increasing by several degrees deeper in the scrape-off layer (SOL).…”

Section: Introductionmentioning

confidence: 99%

Long-term erosion and deposition studies of the main graphite limiter in TEXTOR

Kreter¹,

Kirschner²,

Wienhold³

et al. 2007

Phys. Scr.

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Erosion and deposition behaviour of the TEXTOR main toroidal belt limiter ALT-II has been studied for two generations of limiter tiles with different surface shapes. Two specially prepared tiles with marker holes were subsequently exposed during experimental campaigns with a total plasma duration of > 7000 s and a surface averaged background ion fluence exceeding 2⋅10 25 m -2 . The tile surface relief was measured by optical profilometry and SIMS before and after the exposure. The highest surface erosion of > 10 μm on both tiles was observed in regions with an angle of incidence of the magnetic field α of > ~ 1°, whereas in the regions with α ~ 0.1° both net-erosion and net-deposition were observed depending on the tile shaping. The marker holes were always deposition dominated. Modelling by the ERO code explains qualitatively the surface erosion and deposition behaviour in terms of background flux dilution for shallow angles of incidence.

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“…TEXTOR is a medium size tokamak (major radius 1.75 m, minor radius 0.46 cm) with a circular poloidal plasma cross-section [11]. The position of the last closed flux surface (LCFS) is defined by the toroidal belt limiter ALT-II (Advanced Limiter Test II) [12].…”

mentioning

confidence: 99%

Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR

Kreter

Wienhold

Esser

et al. 2013

Journal of Nuclear Materials

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The 1.1-1.5 mm wide gaps between tiles of the main toroidal belt limiter in TEXTOR were utilized to study the long-term impurity deposition and fuel retention in gaps. The tiles were exposed during a full tokamak campaign of 9365 s of plasma to various discharge conditions and wall conditioning, accumulating of up to 30 µm thick layers at the gap entrance. It was found that (i) gaps trap impurities twice as efficient as the top surface, (ii) the deposition in the toroidal gaps is twice as high as in the poloidal, (iii) carbon deposition decays with a fall-off length of about 0.7 mm towards the gap bottom, (iv) deposition on the bottom is significantly higher than on the adjacent side walls of gaps, (v) the amount of deuterium scales with the amount of carbon with D/C varying from 3% to 30% depending on the surface temperature.

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TEXTOR: A Pioneering Device for New Concepts in Plasma-Wall Interaction, Exhaust, and Confinement

Cited by 33 publications

References 26 publications

Modification of the collective Thomson scattering radiometer in the search for parametric decay on TEXTOR

Modification of the collective Thomson scattering radiometer in the search for parametric decay on TEXTOR

Long-term erosion and deposition studies of the main graphite limiter in TEXTOR

Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR

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