thermal stability of superconducting magnet system in a tokamak
DESCRIPTION
Thermal stability of superconducting magnet system in a tokamak. Dr hab. inż. Leszek Malinowski, prof. PS Dr inż. Monika Lewandowska. Elevation of the ITER magnet system. TF coil conductor design. PF coil conductor design. CS coil conductor. Conductor quantities for ITER magnets. - PowerPoint PPT PresentationTRANSCRIPT
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Thermal stability of superconducting magnet
system in a tokamak
Dr hab. inż. Leszek Malinowski, prof. PS
Dr inż. Monika Lewandowska
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Elevation of the ITER magnet system
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TF coil conductor design
PF coil conductor design
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CS coil conductor
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Conductor quantities for ITER magnets
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Heat loads
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• Conductors made of pure superconducting material are thermally unstable
• Cables constituted of the superconducting material embeded in the normal metal can operate stable.
Thermal stability
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Full stabilizationq > Q
1max
cI
I where oc
c
TThPRI
2
Imax - maximum stable operating current, R - normal state resistance, h - heat transfer
coefficient, P - cooled perimeter, Tc - critical temperature, To - coolant temperature.
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Main disadvantage of fully stable wires is large amount of stabilizer. This implies:
• low overall current density of the conductor• large size and big cost of a superconducting device
Modern superconducting wires are partly stable.
It implies limited amount of energy which can be dissipated in a cable without disturbing its safe operation.
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Critical energy
crEE
E - energy of dissipationEcr - critical energy of the conductor.
Critical energy - the minimum energy of the thermal disturbance destroying the superconductivity
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Mathematical model of normal zone
quu
gu
au
m
sxxxt
e
h
h
h
n
I
T
p
V
T
u
Tn - temperature of the n thermal component
Vh - volumetric flow in the h cooling channel
ph - pressure in the h cooling channel
Th - temperature in the h cooling channel
Ie - current in the e conducting component
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Main goals of studies and anticipated results
• Identification and quantification of energy disturbances and heat sources in superconducting magnet system in a fusion reactor.
• Analysis and modelling of heat transfer phenomena in cable-in-conduit-conductors (CICC) used in fusion reactor magnets.
• Development of an analytical model of a normal zone in CICC.
• Formulation of stability criteria for CICC.• Performance of sample calculations and validation
of the results by comparison with experimental results.