Thermo-hydraulic analysis of the TPX superconducting toroidal field magnets

Author

Wong, Robert L. ; Zbasnik, Jon P. ; Hassenzahl, William V.

Author_Institution

Lawrence Livermore Nat. Lab., CA, USA

Volume

2

fYear

1993

fDate

11-15 Oct 1993

Firstpage

723

Abstract

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

Keywords

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; Boring; Conductors; Heating; Helium; Magnetic analysis; Plasma temperature; Superconducting cables; Superconducting coils; Superconducting filaments and wires; Superconducting magnets;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on

Conference_Location

Hyannis, MA

Print_ISBN

0-7803-1412-3

Type

conf

DOI

10.1109/FUSION.1993.518430

Filename

518430