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Berlin 2014 – scientific programme

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P: Fachverband Plasmaphysik

P 11: Magnetic Confinement II

P 11.7: Talk

Tuesday, March 18, 2014, 16:20–16:35, SPA HS202

Stellarator-specific developments for the systems code PROCESS — •Felix Warmer1, Peter Knight2, Craig Beidler1, Andreas Dinklage1, Yühe Feng1, Joachim Geiger1, Felix Schauer1, Yuriy Turkin1, David Ward2, Robert Wolf1 und Pavlos Xanthopoulos11Max-Planck-Institut für Plasmaphysik, Wendelsteinstraße 1, D-17491 Greifswald, Germany — 2Culham Centre for Fusion Energy, Abingdon, Oxfordshire, OX14 3DB, United Kingdom

The ultimate goal of fusion research is to demonstrate the feasibility of economic production of electricity. The most promising concepts to achieve this by magnetic confinement are the Tokamak and the Stellarator. System codes are used to study the general properties of a fusion power plant. Built in a modular way systems codes describe the physical and technical properties of the power plant components. For the Helical Advanced Stellarator (HELIAS) concept modules have been developed in the frame of the existing Tokamak systems code PROCESS.

These include: A geometry model based on Fourier coefficients which represent the complex 3-D plasma shape, a divertor model which assumes diffusive cross-field transport and high radiation at the X-point, a coil model which uses a scaling based on the HELIAS design and a transport model which either employs empirical confinement time scalings or sophisticated 1-D collisional and turbulent transport calculations. This approach aims at a direct comparison between Tokamak and Stellarator power plant designs.

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