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

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