作者: M.V. Umansky , R.H. Bulmer , R.H. Cohen , T.D. Rognlien , D.D. Ryutov
DOI: 10.1088/0029-5515/49/7/075005
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摘要: Quantitative assessment of the performance high-power tokamak divertors for a range geometric variations is conducted using MHD code Corsica (Crotinger et al 1997 Technical Report LLNL) and edge transport UEDGE (Rognlien 1992 J. Nucl. Mater. 196–198 347). In multi-parametric study divertor compared with standard snowflake (Ryutov 2007 Phys. Plasmas 14 064502) configurations same core plasma parameters. Divertor quantities that are varied include x-point flux expansion, shape target plates, radiating impurity species concentrations. For studied cases, in peak heat load on plates significantly reduced due to larger plasma-wetted area fraction power radiated edge.