Publisher's Synopsis
Excerpt from A Survey of Problems in Divertor and Edge Plasma Theory
On the bases of expected fusion energy production in a fusion reactor and of the energy and particle confinement in tokamaks as presently observed and understood, it is clear that a major design problem for a tokamak reactor is the development of a technique to accept the huge heat and particle ?uxes at the first wall. At the same time there should not be a significant impurity re?ux into the device. The introduction of a divertor is considered the best solution to the problem of absorbing the ?uxes leaving the tokamak while maintaining a pure plasma. The iter cda has identified the divertor design as one of the most difficult design tasks The divertor design has also been a major issue for bpx-cit and tpx. The studies of demo and tokamak reactors also identify the divertor action as a critical item for successful tokamak operation.
Given the importance of the divertor, it is no surprise that some time ago major efforts were established to model the plasma outside the separatrix. Typically these codes, of which many exist worldwide, follow the plasma, heat ?ows, neutrals and impurities in the region from the separatrix to the divertor plates. The system is often conceptually divided into a scrape-off layer adjacent to the core plasma and the somewhat distinct divertor region. These codes demand information from more or less standard fusion plasma physics, the physics of sheaths, and extensive data on atomic and molecular processes and surface physics. The experimental database on the scrape-off layer and divertor is presently rather limited, but in the near future extensive experimental information to compare against model predictions will become available.
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