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Brenner, W.; Gibson, G.; Iwinski, E.
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Fusion Power Systems Dept1975
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Fusion Power Systems Dept1975
AbstractAbstract
[en] A computer code, W-COPE, has been developed to carry out analyses of the Ohmic Heating Coil (OH) and Equilibrium Field Coil (EF) circuits and to scope the required circuit components for the Tokamak Fusion Test Reactor (TFTR). The model which has been formulated has the capability of determining the energy and power requirements of the OH and EF circuits for plasma initiation, maintenance, and compression. For the compression model it is possible to independently force the EF circuit and determine the OH voltage and current requirements to compress without initiating ''skin currents'' in the plasma. The TFTR circuitry as modeled and coded in W-COPE is presented with a description of the scheduled or resultant behavior of various system components both during precompression and compression of the plasma; input constants used in analyses, e.g., resistances and inductances, are given; and the results of typical analyses are also presented and discussed. The energy-storage capacity of the condensers and the ratings of the power supplies required for the conceptual design of the EF and OH circuits for the TFTR are given
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Nov 1975; 32 p; Available from NTIS., PC A03/MF A01
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Report
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