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Simulation of Thermal–Hydraulic Transients in the KSTAR PF1 Coil Using the 4C Code.
- Source :
- IEEE Transactions on Plasma Science; 3/1/2012 Part 1 Part 1, Vol. 40 Issue 3, p710-714, 5p
- Publication Year :
- 2012
-
Abstract
- KSTAR is a fully superconducting tokamak in operation since 2008 at the National Fusion Research Institute in Korea. All coils are wound using cable-in-conduit conductors and cooled with forced-flow supercritical helium at 4.5 K and 5.5 bar. We consider here the central pair, PF1U/L, of the central solenoid coils; during operation, these coils are subjected to sharp current transients, which induce ac losses in the coil. The thermal hydraulic transient following a trapezoidal current pulse, with a ramp-up to 10 kA at a rate of 1 kA/s and a ramp-down to 0 kA at a rate of 10 kA/s, is simulated here using the 4C code, and the results are compared with the measurements. [ABSTRACT FROM PUBLISHER]
- Subjects :
- SIMULATION methods & models
HYDRAULIC transients
TOKAMAKS
SOLENOIDS
ELECTRIC coils
Subjects
Details
- Language :
- English
- ISSN :
- 00933813
- Volume :
- 40
- Issue :
- 3
- Database :
- Complementary Index
- Journal :
- IEEE Transactions on Plasma Science
- Publication Type :
- Academic Journal
- Accession number :
- 73616917
- Full Text :
- https://doi.org/10.1109/TPS.2011.2181874