A computational model describing confinement and performance of circular and D-shaped tokamak plasmas
A combined one- and two-dimensional description of toroidal and axisymmetric plasmas is presented, based on an equilibrium solver resorting to the fast Buneman invertor and two one-dimensional transport codes describing the protium, deuterium, tritium and plasma energy inventory and accounting for three impurity species. It is employed to compute the time evolution of Tokamak plasmas. An attempt is made to achieve consistent modelling of the transport and equilibrium phenomena in a plasma which interact with the peripheral devices for confinement, plasma heating and limitation of the plasma aperture. It is shown that the measured time evolution of the currents in the poloidal field coils of TEXTOR can be reproduced within an accuracy of 8%, if the non-saturated transformer iron is accounted for. The performance of the JET plasma is strongly influenced by the impurities essentially due to sputtering at the non-carbonised linear material (iron). The analysis of the INTOR-plasma shows that at a burn temperature of 10 keV the fusion power exceeds the line radiation, ionisation, conduction, and convection losses by 11 MW. Due to the high pressure gradient, the plasma turns out to be diamagnetic in the total cross section. The toroidal field, however, is reduced at the magnetic axis by 4% of the vacuum value only.
Bibliographic Reference: Article: Journal of Computational Physics, Vol. 80 (1989) No. 1, pp. 98-136
Record Number: 199010582 / Last updated on: 1994-12-01
Original language: en
Available languages: en