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The ITER Divertor Test Facility (IDTF) was designed for the high heat flux tests of outer vertical targets, inner vertical targets and domes of the ITER divertor.
Moreover, the study unravels the gas recirculation effect located behind the vertical targets, viz.
In order to increase the degree of closure, the divertor structure is designed to consist of vertical targets, tightly fitting side baffles and dome baffles.
In the framework of the European DEMO divertor project, several novel design concepts of the plasma-facing components of vertical targets are being developed.
The shaping of the ITER divertor vertical targets has been refined as a consequence of manufacturing and engineering considerations during the prototype manufacturing activities.
The vertical targets in fusion divertors are the main component which are exposed to very high heat flux generally exceeding 10 MW/m2.
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A novel measuring principle of one linear array CCD camera vertical target is presented.
One standard 20 cm × 20 cm uniform flat square vertical target with a reflection factor of 0.50 was used.
The geometrical boundary conditions and the overall shape correspond to the design for the ITER divertor vertical target.
A lower single-null closed divertor with a vertical target (VT) will be installed when experiments begin.
A semi-closed divertor configuration with vertical target is adopted as the first conceptual divertor design on NCT.
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