Standard

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.

In: Fusion Engineering and Design, Vol. 163, No. 163, 112133, 01.02.2021.

Research output: Contribution to journalArticlepeer-review

Harvard

Arslanova, DN, Belov, AV, Gapionok, EI, Kukhtin, VP, Lamzin, EA, Makarov, AA, Ovsyannikov Sr., DA, Ovsyannikov Jr., DA & Сычевский, СЕ 2021, 'Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events', Fusion Engineering and Design, vol. 163, no. 163, 112133. https://doi.org/10.1016/j.fusengdes.2020.112133

APA

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, С. Е. (2021). Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events. Fusion Engineering and Design, 163(163), [112133]. https://doi.org/10.1016/j.fusengdes.2020.112133

Vancouver

Arslanova DN, Belov AV, Gapionok EI, Kukhtin VP, Lamzin EA, Makarov AA et al. Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events. Fusion Engineering and Design. 2021 Feb 1;163(163). 112133. https://doi.org/10.1016/j.fusengdes.2020.112133

Author

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. / Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events. In: Fusion Engineering and Design. 2021 ; Vol. 163, No. 163.

BibTeX

@article{89c3f096d94642719bf28402b9d9a327,
title = "Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events",
abstract = "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.",
keywords = "ITER, DINA scenario, Plasma disruption, Magnet system, Inductive coupling, EM loads, Conducting element, FE model",
author = "D.N. Arslanova and A.V. Belov and E.I. Gapionok and V.P. Kukhtin and E.A. Lamzin and A.A. Makarov and {Ovsyannikov Sr.}, D.A. and {Ovsyannikov Jr.}, D.A. and Сычевский, {Сергей Евгеньевич}",
note = "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.",
year = "2021",
month = feb,
day = "1",
doi = "10.1016/j.fusengdes.2020.112133",
language = "English",
volume = "163",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier",
number = "163",

}

RIS

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