Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events. / Arslanova, D.N.; Belov, A.V.; Gapionok, E.I.; Kukhtin, V.P.; Lamzin, E.A.; Makarov, A.A.; Ovsyannikov Sr., D.A.; Ovsyannikov Jr., D.A.; Сычевский, Сергей Евгеньевич.
в: Fusion Engineering and Design, Том 163, № 163, 112133, 01.02.2021.Результаты исследований: Научные публикации в периодических изданиях › статья › Рецензирование
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TY - JOUR
T1 - Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events
AU - Arslanova, D.N.
AU - Belov, A.V.
AU - Gapionok, E.I.
AU - Kukhtin, V.P.
AU - Lamzin, E.A.
AU - Makarov, A.A.
AU - Ovsyannikov Sr., D.A.
AU - Ovsyannikov Jr., D.A.
AU - Сычевский, Сергей Евгеньевич
N1 - Funding Information: Research was carried out using computational resources provided by Resource Center ?Computer Center of SPbU? (http://cc.spbu.ru) and such support is gratefully acknowledged. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.
PY - 2021/2/1
Y1 - 2021/2/1
N2 - 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.
AB - 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.
KW - ITER
KW - DINA scenario
KW - Plasma disruption
KW - Magnet system
KW - Inductive coupling
KW - EM loads
KW - Conducting element
KW - FE model
UR - http://www.scopus.com/inward/record.url?scp=85097465970&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/d2c59c9a-8162-3b22-85f6-3a7b0b91d20a/
U2 - 10.1016/j.fusengdes.2020.112133
DO - 10.1016/j.fusengdes.2020.112133
M3 - Article
VL - 163
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
IS - 163
M1 - 112133
ER -
ID: 71524553