Community Research and Development Information Service - CORDIS


For future fusion experiments such as ITER, the plasma edge and divertor region is of crucial importance with regard to power and particle control, impurity transport and helium removal. To understand the underlying physics, appropriate models have to be developed and must be validated using experiments in tokamaks such as ASDEX-Upgrade. These models can then also be used to predict the behaviour of future fusion devices or to optimise their design, and also to simulate different installations in present machines, in order to optimise them before installation in the machine. In this paper, first calculations with the B2-EIRENE code package for the design of a divertor baffle for the ASDEX-Upgrade tokamak are presented. This baffle will be installed to enhance the neutral gas pressure in the pumping duct for increased pumping capability.

Additional information

Authors: BOSCH H-S ET AL., Max-Planck-Institut für Plasmaphysik, Garching bei München (DE);REITER D, Forschungszentrum Jülich GmbH (DE);BAELMANS T, Katholieke Universiteit Leuven, Heverlee (BE);BRAAMS B, New York University, Courant Institute (US)
Bibliographic Reference: Article: Proceedings of the 19th Conference on Controlled Fusion and Plasma Physics, Vol. 2 (1992) pp. 747-750
Record Number: 199211304 / Last updated on: 1994-11-29
Original language: en
Available languages: en