Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibria

Journal Article · Wed Aug 01 04:00:00 EDT 1979 · J. Comput. Phys.; (United States)

DOI:https://doi.org/10.1016/0021-9991(79)90129-3· OSTI ID:5972011

Johnson, J L; Dalhed, H E; Greene, J M; Grimm, R C; Hsieh, Y Y; Jardin, S C; Manickam, J; Okabayashi, M; Storer, R G; Todd, A M.M.; Voss, D E; Weimer, K E

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 psi. 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 psi. Examples of the application of the codes to tokamak design at PPPL are given.

• Research Organization: Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08544
• OSTI ID: 5972011
• Journal Information: J. Comput. Phys.; (United States), Journal Name: J. Comput. Phys.; (United States) Vol. 32:2; ISSN JCTPA
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101* -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
ANNULAR SPACE
CLOSED PLASMA DEVICES
CONFIGURATION
DIFFERENTIAL EQUATIONS
EQUATIONS
EQUILIBRIUM
FLUID MECHANICS
HYDRODYNAMICS
ITERATIVE METHODS
MAGNETOHYDRODYNAMICS
MECHANICS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TOROIDAL CONFIGURATION