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

D.N. Arslanova, A.V. Belov, E.I. Gapionok, V.P. Kukhtin, E.A. Lamzin, A.A. Makarov, D.A. Ovsyannikov Sr., D.A. Ovsyannikov Jr., S.E. Sytchevsky

Результат исследований: Научные публикации в периодических изданияхстатья

Аннотация

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.
Язык оригиналаанглийский
Номер статьи112133
ЖурналFusion Engineering and Design
Номер выпуска163
Ранняя дата в режиме онлайн7 дек 2020
DOI
СостояниеОпубликовано - 2021

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