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Abstract

Many of the interesting present and future fusion devices can only be described with three dimensional (3D) equilibria. This holds for all the existing and future stellarators and even tokamaks like JET turn into intermediate 3D equilibria with strong helical structures of the non ergodic inner part of the plasma. The new designs of very expensive fusion devices such as the ATF, WVII-AS or WVII-X and especially ITER constitute a compelling incentive to investigate numerically the 3D stability of such experiments. Here is presented a 3D ideal MHD stability code, named TERPSICHORE based on experiences learned with ERATO, HERA and PEST2. In TERPSICHORE the existence of nested flux surfaces in the equilibrium is assumed and maintained during the stability analysis. Fourier expansion techniques are used in the two angular periodic ( Boozer ) co-ordinates and finite hybrid elements radially. Inverse vector iteration is applied to compute eigenvalues and eigenfunctions. All parts of the code are highly vectorized and parallelizable, which represents one of the aims of the ASTRID project at the EPFL. So far TERPSICHORE is restricted to fixed boundary solutions. First comparisons with results for a straight l=2 stellarator obtained previously with HERA and BETA show satisfactory agreement.

Additional information

Authors: ANDERSON D V, Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Fédérale de Lausanne (CH);COOPER A, Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Fédérale de Lausanne (CH);SCHWENN U, Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Fédérale de Lausanne (CH);GRUBER R, Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Fédérale de Lausanne (CH)
Bibliographic Reference: Paper presented: Theory of Fusion Plasmas, Oct. 3-7 1988
Availability: Available from (1) as Paper EN 34234 ORA
Record Number: 198910520 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en