The design of central column protection tiles for the TCV tokamak

Pitts, R.A.; Chavan, R.; Moret, J.M.

doi:10.1088/0029-5515/39/10/306

Cited by 26 publications

(19 citation statements)

References 20 publications

(18 reference statements)

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“…The specific shape of the TCV tiles [21], shown in Fig. 2a, featuring a line of tangential incidence for limited plasmas, allows to estimate the cross-field heat flux at the limiter q ⊥ .…”

Section: Infrared Data Analysis Methodsmentioning

confidence: 99%

Understanding and suppressing the near scrape-off layer heat flux feature in inboard-limited plasmas in TCV

et al. 2017

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In inboard-limited plasmas, the Scrape-Off Layer (SOL) shows two regions: the near SOL, extending a few mm from the Last Closed Flux Surface (LCFS), characterized by a steep gradient of the parallel heat flux radial profile, and a far SOL, typically some cm wide, with flatter heat flux profiles. The physics of the near SOL is investigated in TCV with two series of experiments featuring deuterium and helium plasmas, in which the plasma current, density and elongation have been varied. The parallel heat flux profiles are measured on the limiter by means of infrared thermography. For the first time, the near SOL is reported to disappear for low plasma current or at high density, for values of the SOL collisionality ν * SOL corresponding to a conduction-limited regime. The power in the near SOL ∆P SOL is shown to decrease with the normalized Spitzer resistivity ν as ∆P SOL ∝ ν −1 . The floating potential profiles, measured at the limiter using flush-mounted Langmuir probes (LP), show the presence of non-ambipolar currents, and their relation to the presence of a velocity shear layer is discussed. The shearing rate is shown to strictly correlate with the power in the near SOL ∆P SOL , consistently with a recent theoretical model. Measurements of the near SOL on the Low Field Side (LFS) are performed using a reciprocating Langmuir probe (RP). The near SOL is reported to vanish simultaneously at the LFS and at the limiter. The near and far SOL widths are compared with the predictions from existing theoretical models, to which empirical corrections with resistivity and elongation are proposed.

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Section: Infrared Data Analysis Methodsmentioning

confidence: 99%

Understanding and suppressing the near scrape-off layer heat flux feature in inboard-limited plasmas in TCV

et al. 2017

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“…A series of dedicated experiments is performed on TCV to investigate the presence of such an enhanced heat flux. In TCV, the inboard limiter is formed by 32 graphite tiles, shaped in order to minimize the heat loads [4]. These tiles constitute a quasi-continuous toroidal limiter, similar to the ITER first wall.…”

Section: Introductionmentioning

confidence: 99%

Heat loads in inboard limited L-mode plasmas in TCV

Nespoli

Labit

Furno

et al. 2015

Journal of Nuclear Materials

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Article history: Available online xxxx a b s t r a c t Infrared thermography is used in TCV to measure the heat flux deposited onto the graphite tiles of the inner wall. The heat flux radial profile is found to be well described by the sum of a main parallel component and a non negligible cross-field component. The latter accounts for about 20% of the deposited heat flux. The parallel component shows an enhancement around the contact point in all discharges under consideration. Main plasma parameters, such as density, current, elongation and triangularity have been varied, allowing for empirical scalings of the heat fluxes.

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“…Fine grained, polycrystalline graphite armour tiles protect the TCV vacuum vessel wall to $90% of the surface area [15]. In particular, the outer target tiles are machined from the graphite type FP 379 supplied by Schunk.…”

Section: Methodsmentioning

confidence: 99%