Title :
Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
Author :
Oh, Dong Keun ; Kim, Keeman ; Lee, Hyun Joung ; Wang, Qiuliang
Author_Institution :
Nat. Fusion Res. Center, Daejeon, South Korea
fDate :
6/1/2009 12:00:00 AM
Abstract :
As an activity to build a new test facility for superconducting CICCs (Cable In Conduit Conductors), an insertion coil for an upgrade of the existing CS (central solenoid) model coil of KSTAR was designed and analysed to implement a superconducting magnet system being capable of pulsed operation up to 12 T. On the basis of a developed winding scheme of the insertion coil, some candidates of CICC design were proposed according to the result of an optimization method and a numerical code examining the thermo-hydraulic stability of CICC. After the design of winding pack and CICCs, we investigated thermo-hydraulic behaviors of the superconducting magnet with respect to given scenarios to estimate the limit of safe operation in pulsed mode.
Keywords :
Tokamak devices; fusion reactor design; fusion reactor operation; fusion reactor safety; fusion reactor theory; superconducting cables; superconducting magnets; windings; CICC design; KSTAR; central solenoid model coil; insertion coil; magnetic flux density 12 T; optimization method; pulsed mode; pulsed operation; safe operation; superconducting cable-in-conduit conductors; superconducting magnet system; test facility; thermohydraulic analysis; upgraded PUMA system; winding pack; winding scheme; Conductors; Magnetic analysis; Optimization methods; Solenoids; Stability analysis; Superconducting cables; Superconducting coils; Superconducting magnets; Test facilities; Thermal stability; CICC; KSTAR; superconducting magnet; thermohydraulic analysis;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2009.2018787
