Achievement of ITER's objectives, long-pulse ignited operation and nuclear component testing in quasi-steady-state, requires exhaust of power and helium ash, control of impurity content, and long lifetimes for plasma-facing components. In this paper we describe the data base and modeling results used to extrapolate present edge plasma parameters to ITER. Particular emphasis has been given to determining the uncertainties in predicted divertor performance. These analyses have been applied to four typical scenarios: A1 (ignited, reference Physics Phase), B1 (long pulse, hybrid, Technology Phase), B6 (steady-state, Technology Phase, impurity seeded) and B4 (steady-state, Technology Phase). 43 refs., 3 tabs.
Cohen, S A; Cummings, J; Post, D E; Redi, M H;  Braams, B J;  Brooks, J;  Engelmann, F; Pacher, G W; Pacher, H D;  Harrison, M; Hotston, E 
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- Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.). NET Design Team
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