Thermo-Hydraulic Analysis of Superconducting Toroidal-Field Magnets for the Tokamak Physics Experiment
The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, 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, the minimum-temperature margin, and the stability against rapid heat input. The results guide the choice and design of the liquid helium refrigerator.
KeywordsLawrence Livermore National Laboratory Conductor Temperature Toroidal Field Poloidal Field Flow Length
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