2013
DOI: 10.1088/1009-0630/15/3/07
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Abstract: An infrared camera (IR) has been put into operation in the Experimental Advanced Superconducting Tokamak (EAST), which is used to measure the temperature distribution on the surface of lower divertor target plates. With a finite difference method, the heat flux onto the divertor target plates is calculated from the surface temperature profile. The high confinement mode (H-mode) with type-III edge localized modes (ELMs) has been obtained with about 1 MW lower-hybrid wave power on the EAST in the autumn experime… Show more

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Cited by 9 publications
(4 citation statements)
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“…In this work, the heat flux widths were measured by three independent diagnostics, i.e., divertor triple LP arrays embedded in the target plates [17], the IR camera [18] whose view-field covers the divertor region, and fast reciprocating LPs at the outer mid-plane [19], as shown in figure 1. The parallel heat fluxes measured by LPs are calculated using the standard sheath model [23], i.e., q = γ n t C st T t , where n t and T t are the electron density and electron temperature at the target, respectively.…”
Section: Heat Flux Diagnostics and Experimental Programmementioning
confidence: 99%
See 1 more Smart Citation
“…In this work, the heat flux widths were measured by three independent diagnostics, i.e., divertor triple LP arrays embedded in the target plates [17], the IR camera [18] whose view-field covers the divertor region, and fast reciprocating LPs at the outer mid-plane [19], as shown in figure 1. The parallel heat fluxes measured by LPs are calculated using the standard sheath model [23], i.e., q = γ n t C st T t , where n t and T t are the electron density and electron temperature at the target, respectively.…”
Section: Heat Flux Diagnostics and Experimental Programmementioning
confidence: 99%
“…This paper will present the detailed study on the divertor power footprint width scaling with I p (equivalently related to the poloidal field at the outer mid-plane B p,omp or the edge safety factor q 95 at the 95% poloidal flux surface) in RF-heated H-modes on EAST. The experimental data were obtained by various diagnostics, which evaluate the divertor heat flux width or upstream SOL width simultaneously, i.e., (1) divertor triple Langmuir probe (LP) arrays [17], (2) the infra-red (IR) camera [18] and (3) the fast reciprocating LPs at the low-fieldside (LFS) mid-plane [19]. The investigation of the divertor power footprint width scaling was systematically performed, for the first time, under various divertor configurations on a superconducting tokamak similar to ITER.…”
Section: Introductionmentioning
confidence: 99%
“…The total radiated power of the whole plasma P rad is measured by the resistive bolometer, 37 and the power loading on the divertor targets P div is measured by the infra-red (IR) camera. 38 The portion of radiated power in the total input power is 30%-40%, and the divertor target power is about 40%-60% of the input power. For the three shots #41606 (DN), #41608 (LSN), and #41610 (USN), the total radiated power increases $10% due to the helium gas injection.…”
Section: Resultsmentioning
confidence: 99%
“…An upgraded wide-angle IR camera system, which could provide a real-time platform to monitor the temperature distribution on PFCs, was commissioned in 2012. Compared to the previous diagnostic system with one IR camera taking a tangential view to the lower divertor plates region [9] , the new system has the advantage of being able to simultaneously observe upper and lower divertors, the protection limiter of the LHW antenna and the movable limiter. Fig.…”
Section: Methodsmentioning
confidence: 99%