Thermo-hydraulic Analysis of the TPX Superconducting Toroidal Field Magnets
Fusion Engineering, 1993, 15th IEEE/NPSS Symposium（1993）
摘要
The superconducting magnets in fusion reactors are subjected to heating from the pulsed operation of the poloidal field (PF) magnets, nuclear, eddy-current, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics Experiment (TPX). We present results of design studies that determine the trade-off between double- and single-pancake helium-flow configurations
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关键词
Tokamak devices,eddy currents,fusion reactor design,fusion reactor materials,fusion reactor operation,fusion reactors,helium,nuclear engineering computing,plasma heating,plasma toroidal confinement,superconducting magnets,He,TPX superconducting toroidal field magnets,Tokamak Physics Experiment,computer codes,conductor response,design studies,double-pancake flow configurations,eddy-current heating,forced-flow cooled conductors,fusion reactors,heat sources,magnet design,magnet performance,nuclear heating,poloidal field magnets,pulsed operation heating,resistive heating,single-pancake flow configurations,thermohydraulic analysis,toroidal field magnets
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