Divertor and confinement issues for next-step devices.

Next step devices operating in advanced tokamak (AT) modes include proposed experiments (including NHTX and FDF), Component Test Facilities (CTFs), and ITER. We present an analysis of the likely scrape-off layer widths and heat loads on the divertors for such devices. We include analysis of novel divertor configurations including X-divertors and stochastic edge. The connection between divertor modifications and core plasma confinement is also examined.