Abstract
The purpose of the work is to to develop a two-dimensional Finite-Element-Code. This code should be able to simulate the plasma flow pattern in the burning chamber of fusion devices by an exact and solution-dependent discretisation. Reionisation and other collision processes of recycled neutral particles are described by coupling the fluid model to the kinetic Monte-Carlo neutral-gas-code EIRENE. For comparison and fundamental numerical studies a fast analytical description of recycling is also available. Such rather crude approximations are employed in other codes often as the only option. It is possible to treat the flow of ions and neutral atoms/molecules near complex surface structures of fusion devices consistently. Because of the time step restriction in the special solution algorithm, up to now the electron temperature profile has to be provided from elsewhere. It can, for example be interpolated from experimental data or from results of other independent code calculations. The newly developed code is applied to a typical TOKAMAK-discharge (TEXTOR) and characteristic results are discussed. (orig./HP)
Citation Formats
Puetz, T.
Development of a FE method for modelling plasma flows in tokamak plasma edges; Entwicklung eines Finite Elemente Verfahrens zur Modellierung der Plasmastroemung in der Randschicht von TOKAMAKS.
Germany: N. p.,
1994.
Web.
Puetz, T.
Development of a FE method for modelling plasma flows in tokamak plasma edges; Entwicklung eines Finite Elemente Verfahrens zur Modellierung der Plasmastroemung in der Randschicht von TOKAMAKS.
Germany.
Puetz, T.
1994.
"Development of a FE method for modelling plasma flows in tokamak plasma edges; Entwicklung eines Finite Elemente Verfahrens zur Modellierung der Plasmastroemung in der Randschicht von TOKAMAKS."
Germany.
@misc{etde_10128430,
title = {Development of a FE method for modelling plasma flows in tokamak plasma edges; Entwicklung eines Finite Elemente Verfahrens zur Modellierung der Plasmastroemung in der Randschicht von TOKAMAKS}
author = {Puetz, T}
abstractNote = {The purpose of the work is to to develop a two-dimensional Finite-Element-Code. This code should be able to simulate the plasma flow pattern in the burning chamber of fusion devices by an exact and solution-dependent discretisation. Reionisation and other collision processes of recycled neutral particles are described by coupling the fluid model to the kinetic Monte-Carlo neutral-gas-code EIRENE. For comparison and fundamental numerical studies a fast analytical description of recycling is also available. Such rather crude approximations are employed in other codes often as the only option. It is possible to treat the flow of ions and neutral atoms/molecules near complex surface structures of fusion devices consistently. Because of the time step restriction in the special solution algorithm, up to now the electron temperature profile has to be provided from elsewhere. It can, for example be interpolated from experimental data or from results of other independent code calculations. The newly developed code is applied to a typical TOKAMAK-discharge (TEXTOR) and characteristic results are discussed. (orig./HP)}
place = {Germany}
year = {1994}
month = {Jul}
}
title = {Development of a FE method for modelling plasma flows in tokamak plasma edges; Entwicklung eines Finite Elemente Verfahrens zur Modellierung der Plasmastroemung in der Randschicht von TOKAMAKS}
author = {Puetz, T}
abstractNote = {The purpose of the work is to to develop a two-dimensional Finite-Element-Code. This code should be able to simulate the plasma flow pattern in the burning chamber of fusion devices by an exact and solution-dependent discretisation. Reionisation and other collision processes of recycled neutral particles are described by coupling the fluid model to the kinetic Monte-Carlo neutral-gas-code EIRENE. For comparison and fundamental numerical studies a fast analytical description of recycling is also available. Such rather crude approximations are employed in other codes often as the only option. It is possible to treat the flow of ions and neutral atoms/molecules near complex surface structures of fusion devices consistently. Because of the time step restriction in the special solution algorithm, up to now the electron temperature profile has to be provided from elsewhere. It can, for example be interpolated from experimental data or from results of other independent code calculations. The newly developed code is applied to a typical TOKAMAK-discharge (TEXTOR) and characteristic results are discussed. (orig./HP)}
place = {Germany}
year = {1994}
month = {Jul}
}