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Abstract

SOL modelling results for the SST-1 show a sheath limited flow regime. This due to the loe edge densities required by lower hybrid current drive (LJCD), coupled with high power input per unit volume. Coupled plasma-neutral transport studies using B2-Eirene show significantly high charge exchange losses and radiated power from the core. It also shows that the heat flux to the inner divertor is higher than that to the outer divertor due to thinner inner SOL widths. The Monte Carlo neutral transport code DEGAS was used to optimise the baffle plate geometry and it was seen that a configuration where the baffle plate shields the main plasma from the divertor strike point results in reduced backflow of neutrals. The divertor erosion code DIVER was used to predict a steady state operating temperature for the SST divertor plate lying in the range 750-1000 Degrees Celsius for which the erosion will be minimum.

Additional information

Authors: WARRIER M, Institute for Plasma Research, BHAT, Gujrat (IN);JAISHANKAR S, Institute for Plasma Research, BHAT, Gujrat (IN);DESHPANDE S, Institute for Plasma Research, BHAT, Gujrat (IN);CHATURVEDI S, Institute for Plasma Research, BHAT, Gujrat (IN);SRINIVASAN R, Institute for Plasma Research, BHAT, Gujrat (IN);COSTER D, Max-Planck-Institut fur Plasmaphysik, Garching (DE);SCNIEDER R, Max-Planck-Institut fur Plasmaphysik, Garching (DE);BRAAMS B J, Courant Institute of Mathematical Sciences
Bibliographic Reference: Article: Journal of Nuclear Materials, 266-269 (1999), 726-731
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