Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events

Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events

•Duration of DINA-plasma disruption scenarios is limited by the end of plasma CQ.•Using of constant CS and PF coil currents after CQ end may give incorrect results.•Inductive coupling between the CS and PF coils and VV.•EM loads on the tokamak components located outside VV. One of the most crucial i...

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Bibliographic Details
Published in:Fusion engineering and design Vol. 163; p. 112133
Main Authors: Arslanova, D.N., Belov, A.V., Gapionok, E.I., Kukhtin, V.P., Lamzin, E.A., Makarov, A.A., Ovsyannikov, D.A., Sytchevsky, S.E.
Format: Journal Article
Language:English
Published: Amsterdam Elsevier B.V 01-02-2021
Elsevier Science Ltd
Subjects:
Conducting element
DINA scenario
Disruption
Eddy currents
EM loads
FE model
Field coils
Inductive coupling
ITER
Loads (forces)
Magnet system
Magnets
Mathematical analysis
Plasma
Plasma currents
Plasma disruption
Toroidal plasmas
Vessels
Magnet system
EM loads
DINA scenario
Conducting element
FE model
ITER
Plasma disruption
Inductive coupling
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Summary:•Duration of DINA-plasma disruption scenarios is limited by the end of plasma CQ.•Using of constant CS and PF coil currents after CQ end may give incorrect results.•Inductive coupling between the CS and PF coils and VV.•EM loads on the tokamak components located outside VV. One of the most crucial issues in the design of the ITER machine is the electromagnetic (EM) loads associated with eddy currents induced in the conducting structures during plasma disruptions. The ITER database contains tens of calculation scenarios for possible plasma disruption events. The duration of these scenarios is usually limited by the end of the plasma current quench when the toroidal plasma current decreases to zero. For further EM analysis, the currents in the poloidal field coils are conventionally assumed constant after the end of the current quench. Such approach is not good for estimation of electromagnetic loads acting on the tokamak components located outside vacuum vessel. A possible way to solve this problem is to employ pre-determined coil current variations over the entire period of observation including time interval after the current quench. This paper describes an approach to such electromagnetic calculations and comparative results for selected cases with/out an extended current-time specification.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2020.112133