A method for estimating tokamak poloidal field coil currents which incorporates engineering constraints

Technical Report · Tue May 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6541751· OSTI ID:6541751

Stewart, W A

This thesis describes the development of a design tool for the poloidal field magnet system of a tokamak. Specifically, an existing program for determining the poloidal field coil currents has been modified to: support the general case of asymmetric equilibria and coil sets, determine the coil currents subject to constraints on the maximum values of those currents, and determine the coil currents subject to limits on the forces those coils may carry. The equations representing the current limits and coil force limits are derived and an algorithm based on Newton's method is developed to determine a set of coil currents which satisfies those limits. The resulting program allows the designer to quickly determine whether or not a given coil set is capable of supporting a given equilibrium. 25 refs.

• Research Organization: Massachusetts Inst. of Tech., Cambridge, MA (USA). Plasma Fusion Center
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC02-78ET51013
• OSTI ID: 6541751
• Report Number(s): DOE/ET/51013-T231; PFC/RR-90-8; ON: DE91001662; TRN: 91-000101
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
MAGNET COILS
DESIGN
ALGORITHMS
ASYMMETRY
CURRENT DENSITY
ELECTROMOTIVE FORCE
EQUATIONS
NEWTON METHOD
SUPERCONDUCTING COILS
TOKAMAK DEVICES
CLOSED PLASMA DEVICES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
EQUIPMENT
ITERATIVE METHODS
MATHEMATICAL LOGIC
THERMONUCLEAR DEVICES
700202* - Fusion Power Plant Technology- Magnet Coils & Fields