1. 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

2. • 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

3. 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“