Quench Detection in the ITER Magnet System

The quench detection system in ITER superconducting magnet systems is a real challenge for the poloidal field (PF) system and the central solenoid (CS) due to their fast-pulsed operation. An existing CEA code allowing very precise magnetic field calculations in tokamaks (Traps) has been upgraded (Tr...

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Bibliographic Details
Published in:IEEE transactions on applied superconductivity 2010-06, Vol.20 (3), p.427-430
Main Authors: Coatanea, M, Duchateau, J L, Hertout, P, Bessette, D, Rodriguez-Mateos, F
Format: Article
Language:English
Subjects:
Applied sciences
Coiling
Conductors
Electric potential
Electrical engineering. Electrical power engineering
Electromagnets
Exact sciences and technology
ITER
Magnetic field measurement
Magnetic fields
Mathematical analysis
pancake
Plasmas
quench
Solenoids
Strips
Superconducting coils
Superconducting magnets
Superconductivity
Tokamaks
Toroidal magnetic fields
Various equipment and components
Voltage
voltage detection
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Summary:The quench detection system in ITER superconducting magnet systems is a real challenge for the poloidal field (PF) system and the central solenoid (CS) due to their fast-pulsed operation. An existing CEA code allowing very precise magnetic field calculations in tokamaks (Traps) has been upgraded (TrapsAv) to calculate the inductive voltages induced across any coil sub-element during a plasma scenario. The envisaged primary detection system is based on voltage measurements. For the CS, a detection system is proposed and discussed based on the central difference average balance of 3 neighboring double pancakes. For the TF system, the presently considered compensation circuit in ITER is a strip co-wound on to the conductor. A simple analytical calculation is proposed to estimate the voltage during a plasma disruption or during the scenario across the co-wound strip and across the conductor as well, due to the toroidal component of the plasma current.
ISSN:1051-8223
1558-2515
DOI:10.1109/TASC.2009.2039705