|Title||Thermographic investigation of the effect of plasma exposure on the surface of a MAST upgrade divertor tile in Magnum-PSI|
|Publication Type||Journal Article|
|Year of Publication||2020|
|Authors||M.J Dunn, T.W Morgan, J.W Genuit, T. Loewenhoff, A.J Thornton, K.J Gibson, Magnum PSI team|
|Journal||Nuclear Materials and Energy|
One of the issues faced by future fusion devices will be high divertor target heat loads. Alternative divertors can promote detachment, flux expansion and dissipation mechanisms to mitigate these heat loads. They have been investigated in several devices including TCV and DIII-D, and will be investigated on MAST-U. To evaluate their effectiveness, accurate target heat flux and power balance measurements are required in these machines. Infrared (IR) thermography is a widely used technique to determine the target heat flux, but is susceptible to surface effects and emissivity in carbon-walled machines. In this work, the effect of plasma exposure on graphite is assessed to understand what may happen in MAST-U. A sample of fine grain graphite, as used on MAST-U, is exposed to 30min plasma exposures, with density ne=6 × 1018m−3 and temperature Te=0.08eV as measured by Thomson scattering. During these pulses, the temperature is measured by a medium wave IR camera and is seen to decrease by ≈70 °C over the course of 3h of plasma exposure. Pyrometer measurements suggest that the IR camera data is affected by a change in the surface emissivity. Profilometry confirms erosion of graphite at the tile centre to a depth of ≈100µm, and a larger region of deposition further out, amounting to ≈40µm of material
|Alternate Title||Nucl. Mater. Energy|
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