Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST
This study systematically compares the influence of shattered pellet injection (SPI) and massive gas injection (MGI) on plasma disruption mitigation within the Experimental Advanced Superconducting Tokamak. The results reveal that SPI demonstrates significant advantages over MGI in plasma disruption...
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| Format: | Article |
| Language: | English |
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IOP Publishing
2024-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/ad9939 |
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| author | S.B. Zhao J.S. Yuan H.D. Zhuang G.Z. Zuo L. Li T. Tang L. Zeng Y.M. Duan T.H. Shi S.T. Mao D.L. Chen M. Huang Y. Chen J.S. Hu |
| author_facet | S.B. Zhao J.S. Yuan H.D. Zhuang G.Z. Zuo L. Li T. Tang L. Zeng Y.M. Duan T.H. Shi S.T. Mao D.L. Chen M. Huang Y. Chen J.S. Hu |
| author_sort | S.B. Zhao |
| collection | DOAJ |
| description | This study systematically compares the influence of shattered pellet injection (SPI) and massive gas injection (MGI) on plasma disruption mitigation within the Experimental Advanced Superconducting Tokamak. The results reveal that SPI demonstrates significant advantages over MGI in plasma disruption mitigation, as it predominantly deposits impurities within the plasma core. This leads to more rapid emission of thermal radiation and a significantly shorter total disruption duration compared to MGI. Conversely, MGI primarily deposits impurities at the plasma edge, and its impurity penetration duration is longer compared to that of SPI. During the current quench phase, MGI displays an evident radiation tail extending from the plasma core to its edge, accompanied by a second current spike. These phenomena are primarily attributed to cold vertical displacement events, which cause the plasma to directly contact the first wall, thereby generating halo currents and emitting hard x-rays. Furthermore, both SPI and MGI exhibit clear magnetohydrodynamic (MHD) mode switching, wherein the inherent n = 1 and n = 2 modes transition to a new n = 1 mode. This new mode features a reversed rotation direction and is accompanied by a burst of soft x-rays from the plasma core. This observation suggests that the observed MHD mode switching is driven by impurity‒plasma interactions rather than the impurity injection method. Future research endeavors must focus on high-resolution diagnostics and further experimentation to better understand the impacts of impurities on MHD modes. Overall, this study provides crucial data support for improving plasma disruption mitigation strategies for ITER and other future fusion reactors. |
| format | Article |
| id | doaj-art-3eb9747ef35d4a988bd48b4d99a0f313 |
| institution | OA Journals |
| issn | 0029-5515 |
| language | English |
| publishDate | 2024-01-01 |
| publisher | IOP Publishing |
| record_format | Article |
| series | Nuclear Fusion |
| spelling | doaj-art-3eb9747ef35d4a988bd48b4d99a0f3132025-08-20T02:33:42ZengIOP PublishingNuclear Fusion0029-55152024-01-0165101604810.1088/1741-4326/ad9939Characteristics of plasma disruption mitigation achieved by MGI and SPI on EASTS.B. Zhao0J.S. Yuan1H.D. Zhuang2G.Z. Zuo3https://orcid.org/0000-0002-4149-089XL. Li4T. Tang5L. Zeng6https://orcid.org/0000-0003-4968-1401Y.M. Duan7T.H. Shi8https://orcid.org/0000-0002-5321-1464S.T. Mao9D.L. Chen10https://orcid.org/0000-0001-7093-3154M. Huang11Y. Chen12J.S. Hu13Institute of Plasma Physics , 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 , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , 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 , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaDepartment of Engineering Physics, Tsinghua University , Beijing 100084, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaInstitute of Plasma Physics , Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, ChinaThis study systematically compares the influence of shattered pellet injection (SPI) and massive gas injection (MGI) on plasma disruption mitigation within the Experimental Advanced Superconducting Tokamak. The results reveal that SPI demonstrates significant advantages over MGI in plasma disruption mitigation, as it predominantly deposits impurities within the plasma core. This leads to more rapid emission of thermal radiation and a significantly shorter total disruption duration compared to MGI. Conversely, MGI primarily deposits impurities at the plasma edge, and its impurity penetration duration is longer compared to that of SPI. During the current quench phase, MGI displays an evident radiation tail extending from the plasma core to its edge, accompanied by a second current spike. These phenomena are primarily attributed to cold vertical displacement events, which cause the plasma to directly contact the first wall, thereby generating halo currents and emitting hard x-rays. Furthermore, both SPI and MGI exhibit clear magnetohydrodynamic (MHD) mode switching, wherein the inherent n = 1 and n = 2 modes transition to a new n = 1 mode. This new mode features a reversed rotation direction and is accompanied by a burst of soft x-rays from the plasma core. This observation suggests that the observed MHD mode switching is driven by impurity‒plasma interactions rather than the impurity injection method. Future research endeavors must focus on high-resolution diagnostics and further experimentation to better understand the impacts of impurities on MHD modes. Overall, this study provides crucial data support for improving plasma disruption mitigation strategies for ITER and other future fusion reactors.https://doi.org/10.1088/1741-4326/ad9939shattered pellet injection (SPI)massive gas injection (MGI)cold vertical displacement event (VDE)disruption mitigationExperimental Advanced Superconducting Tokamak (EAST) |
| spellingShingle | S.B. Zhao J.S. Yuan H.D. Zhuang G.Z. Zuo L. Li T. Tang L. Zeng Y.M. Duan T.H. Shi S.T. Mao D.L. Chen M. Huang Y. Chen J.S. Hu Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST Nuclear Fusion shattered pellet injection (SPI) massive gas injection (MGI) cold vertical displacement event (VDE) disruption mitigation Experimental Advanced Superconducting Tokamak (EAST) |
| title | Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST |
| title_full | Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST |
| title_fullStr | Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST |
| title_full_unstemmed | Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST |
| title_short | Characteristics of plasma disruption mitigation achieved by MGI and SPI on EAST |
| title_sort | characteristics of plasma disruption mitigation achieved by mgi and spi on east |
| topic | shattered pellet injection (SPI) massive gas injection (MGI) cold vertical displacement event (VDE) disruption mitigation Experimental Advanced Superconducting Tokamak (EAST) |
| url | https://doi.org/10.1088/1741-4326/ad9939 |
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