Major aims of IPP-NIFS collaboration on divertor physics

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Glenn Bateman Lehigh University Physics Department

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Presentation transcript:

Major aims of IPP-NIFS collaboration on divertor physics • Development and optimization of concepts for controlled plasma exhaust (ID, HD) in helical devices • Progress in understanding of 3D edge transport • Exchange information on experimental and modeling results

• Magnetic topology: sensitivity to magnetic perturbations Topics • Magnetic topology: sensitivity to magnetic perturbations • Plasma transport in SOL: - diffusive, convective, stochastic? - detachment: existence conditions, stability and control - role of plasma drifts and currents • Neutral gas: - recycling, screening, baffling - high neutral compression as pre-condition for active particle pumping and density control • PSI: - target shaping, leading edges, control of max. thermal load - long pulse wall recycling - impurities: sputtering sources, transport, retention, edge radiation • Core-SOL boundary: - Control of upstream edge parameters (including pedestal physics) - Compatibility of reactor-relevant core confinement with high-density divertor plasma Undispensable tools • Adequate diagnostics fullfilling requirements of 3D edge plasmas • Adequate 3D edge transport code for divertor design and physics prediction and interpretation

In this workshop • Two major contributions on 3D divertor transport: - M. Kobayashi (NIFS): Divertor transport study in LHD - Y. Feng (IPP): Features of Divertor Plasmas in W7-AS • Definition of structure and content of a joint paper on divertor transport for ISW Toki 2007 • Tentative title: „Comparative study on divertor transport for W7-AS and LHD“