Abstract
Numerical schemes for the determination of stationary axisymmetric toroidal equilibria appropriate for modeling real experimental devices are given. Iterative schemes are used to solve the elliptic nonlinear partial differential equation for the poloidal flux function ψ. The principal emphasis is on solving the free boundary (plasma-vacuum interface) equilibrium problem where external current-carrying toroidal coils support the plasma column, but fixed boundary (e.g., conducting shell) cases are also included. The toroidal current distribution is given by specifying the pressure and either the poloidal current or the safety factor profiles as functions of ψ. Examples of the application of the codes to tokamak design at PPPL are given.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 212-234 |
| Number of pages | 23 |
| Journal | Journal of Computational Physics |
| Volume | 32 |
| Issue number | 2 |
| DOIs | |
| State | Published - Aug 1979 |
All Science Journal Classification (ASJC) codes
- Numerical Analysis
- Modeling and Simulation
- Physics and Astronomy (miscellaneous)
- General Physics and Astronomy
- Computer Science Applications
- Computational Mathematics
- Applied Mathematics
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