High-Z material erosion and its control in DIII-D carbon divertor

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Abstract

As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W is found to be strongly suppressed by local injection of methane and deuterium gases. The 13C deposition resulting from local 13CH4 injection also provides information on radial transport due to E × B drifts and cross field diffusion. Finally, D2 gas puffing is found to cause local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.

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Ding, R., Rudakov, D. L., Stangeby, P. C., Wampler, W. R., Abrams, T., Brezinsek, S., … Watkins, J. G. (2017). High-Z material erosion and its control in DIII-D carbon divertor. Nuclear Materials and Energy, 12, 247–252. https://doi.org/10.1016/j.nme.2017.03.012

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