Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST

Plasma disruptions present considerable risks to tokamak devices, necessitating the implementation of advanced mitigation techniques such as shattered pellet injection (SPI). This study examines the influence of various shatter tube designs on disruption mitigation characteristics in EAST. The stand...

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Main Authors: L. Li, J.S. Yuan, S.B. Zhao, Y.M. Duan, H.D. Zhuang, D.L. Chen, A. Ti, W. Xia, S.T. Mao, F.D. Wang, T.H. Shi, J.H. Yang, B. Zhang, M. Huang, Y. Chen, G.Z. Zuo, J.S. Hu
Format: Article
Language:English
Published: IOP Publishing 2025-01-01
Series:Nuclear Fusion
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Online Access:https://doi.org/10.1088/1741-4326/adeb9c
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author L. Li
J.S. Yuan
S.B. Zhao
Y.M. Duan
H.D. Zhuang
D.L. Chen
A. Ti
W. Xia
S.T. Mao
F.D. Wang
T.H. Shi
J.H. Yang
B. Zhang
M. Huang
Y. Chen
G.Z. Zuo
J.S. Hu
author_facet L. Li
J.S. Yuan
S.B. Zhao
Y.M. Duan
H.D. Zhuang
D.L. Chen
A. Ti
W. Xia
S.T. Mao
F.D. Wang
T.H. Shi
J.H. Yang
B. Zhang
M. Huang
Y. Chen
G.Z. Zuo
J.S. Hu
author_sort L. Li
collection DOAJ
description Plasma disruptions present considerable risks to tokamak devices, necessitating the implementation of advanced mitigation techniques such as shattered pellet injection (SPI). This study examines the influence of various shatter tube designs on disruption mitigation characteristics in EAST. The standard 20°-bend shatter tube was replaced with a horizontal straight tube to develop an insufficiently SPI (ISPI) system, producing larger and off-axis injected fragments without velocity reduction for comparative analysis with conventional SPI. It was found that after impurity injection, the n = 1 mode in the toroidal signals grows regardless of whether a magnetohydrodynamic (MHD) mode was present in the plasma before injection. Diagnostic assessments indicate that ISPI results in a pre-thermal quench (pre-TQ) duration about 1.5 times longer than SPI attributed to reduced impurity assimilation and a current quench duration 0.83 times shorter than SPI attributed to the fast I _p dissipation via halo current caused by the cold vertical displacement event (VDE). Although ISPI facilitates a slightly more uniform poloidal radiation distribution during the TQ phase, it is associated with weaker mitigation of halo currents, with a mitigation rate of 27.3% compared to SPI’s 64.7%. These findings provide critical insights for optimizing ITER’s SPI strategy by balancing radiation homogeneity, electromagnetic load management, and MHD stability.
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spelling doaj-art-dab704be65064c299cc035e7e9e649e52025-08-20T03:27:19ZengIOP PublishingNuclear Fusion0029-55152025-01-0165808601210.1088/1741-4326/adeb9cEffects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EASTL. Li0J.S. Yuan1S.B. Zhao2Y.M. Duan3H.D. Zhuang4D.L. Chen5https://orcid.org/0000-0001-7093-3154A. Ti6W. Xia7https://orcid.org/0000-0002-4140-8868S.T. Mao8F.D. Wang9https://orcid.org/0000-0002-2462-7145T.H. Shi10https://orcid.org/0000-0002-5321-1464J.H. Yang11B. Zhang12https://orcid.org/0000-0003-0304-2372M. Huang13Y. Chen14G.Z. Zuo15https://orcid.org/0000-0002-4149-089XJ.S. Hu16Institute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China; University of Science and Technology of China , Hefei 230026, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China; University of Science and Technology of China , Hefei 230026, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China; University of Science and Technology of China , Hefei 230026, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics Chinese Academy of Sciences , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaPlasma disruptions present considerable risks to tokamak devices, necessitating the implementation of advanced mitigation techniques such as shattered pellet injection (SPI). This study examines the influence of various shatter tube designs on disruption mitigation characteristics in EAST. The standard 20°-bend shatter tube was replaced with a horizontal straight tube to develop an insufficiently SPI (ISPI) system, producing larger and off-axis injected fragments without velocity reduction for comparative analysis with conventional SPI. It was found that after impurity injection, the n = 1 mode in the toroidal signals grows regardless of whether a magnetohydrodynamic (MHD) mode was present in the plasma before injection. Diagnostic assessments indicate that ISPI results in a pre-thermal quench (pre-TQ) duration about 1.5 times longer than SPI attributed to reduced impurity assimilation and a current quench duration 0.83 times shorter than SPI attributed to the fast I _p dissipation via halo current caused by the cold vertical displacement event (VDE). Although ISPI facilitates a slightly more uniform poloidal radiation distribution during the TQ phase, it is associated with weaker mitigation of halo currents, with a mitigation rate of 27.3% compared to SPI’s 64.7%. These findings provide critical insights for optimizing ITER’s SPI strategy by balancing radiation homogeneity, electromagnetic load management, and MHD stability.https://doi.org/10.1088/1741-4326/adeb9cSPINe shattered pelletsdisruption mitigationEAST
spellingShingle L. Li
J.S. Yuan
S.B. Zhao
Y.M. Duan
H.D. Zhuang
D.L. Chen
A. Ti
W. Xia
S.T. Mao
F.D. Wang
T.H. Shi
J.H. Yang
B. Zhang
M. Huang
Y. Chen
G.Z. Zuo
J.S. Hu
Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
Nuclear Fusion
SPI
Ne shattered pellets
disruption mitigation
EAST
title Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
title_full Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
title_fullStr Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
title_full_unstemmed Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
title_short Effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on EAST
title_sort effects on characteristics of plasma disruption mitigation using shattered pellet injection with different shatter tubes on east
topic SPI
Ne shattered pellets
disruption mitigation
EAST
url https://doi.org/10.1088/1741-4326/adeb9c
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