Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption
Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper i...
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Gespeichert in:
| Autor*in: |
Liu, Sumei [verfasserIn] |
|---|
| Format: |
Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2014 |
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| Schlagwörter: |
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| Anmerkung: |
© Springer Science+Business Media New York 2014 |
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| Übergeordnetes Werk: |
Enthalten in: Journal of fusion energy - Springer US, 1981, 33(2014), 6 vom: 06. Juli, Seite 713-719 |
|---|---|
| Übergeordnetes Werk: |
volume:33 ; year:2014 ; number:6 ; day:06 ; month:07 ; pages:713-719 |
| Links: |
|---|
| DOI / URN: |
10.1007/s10894-014-9736-z |
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OLC2070460894 |
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| 520 | |a Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. | ||
| 650 | 4 | |a CFETR | |
| 650 | 4 | |a Vacuum vessel | |
| 650 | 4 | |a Electromagnetic analysis | |
| 650 | 4 | |a Eddy current | |
| 650 | 4 | |a Plasma major disruption | |
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| 700 | 1 | |a Chen, Mingfeng |4 aut | |
| 700 | 1 | |a Lei, Mingzhun |4 aut | |
| 700 | 1 | |a Lu, Mingxuan |4 aut | |
| 700 | 1 | |a Wang, Zhongwei |4 aut | |
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10.1007/s10894-014-9736-z doi (DE-627)OLC2070460894 (DE-He213)s10894-014-9736-z-p DE-627 ger DE-627 rakwb eng 530 VZ 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. CFETR Vacuum vessel Electromagnetic analysis Eddy current Plasma major disruption Mechanical analysis Chen, Mingfeng aut Lei, Mingzhun aut Lu, Mingxuan aut Wang, Zhongwei aut Enthalten in Journal of fusion energy Springer US, 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)130512575 (DE-600)764392-5 (DE-576)016085973 0164-0313 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 33.00 VZ AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)OLC2070460894 (DE-He213)s10894-014-9736-z-p DE-627 ger DE-627 rakwb eng 530 VZ 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. CFETR Vacuum vessel Electromagnetic analysis Eddy current Plasma major disruption Mechanical analysis Chen, Mingfeng aut Lei, Mingzhun aut Lu, Mingxuan aut Wang, Zhongwei aut Enthalten in Journal of fusion energy Springer US, 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)130512575 (DE-600)764392-5 (DE-576)016085973 0164-0313 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 33.00 VZ AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)OLC2070460894 (DE-He213)s10894-014-9736-z-p DE-627 ger DE-627 rakwb eng 530 VZ 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. CFETR Vacuum vessel Electromagnetic analysis Eddy current Plasma major disruption Mechanical analysis Chen, Mingfeng aut Lei, Mingzhun aut Lu, Mingxuan aut Wang, Zhongwei aut Enthalten in Journal of fusion energy Springer US, 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)130512575 (DE-600)764392-5 (DE-576)016085973 0164-0313 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 33.00 VZ AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)OLC2070460894 (DE-He213)s10894-014-9736-z-p DE-627 ger DE-627 rakwb eng 530 VZ 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. CFETR Vacuum vessel Electromagnetic analysis Eddy current Plasma major disruption Mechanical analysis Chen, Mingfeng aut Lei, Mingzhun aut Lu, Mingxuan aut Wang, Zhongwei aut Enthalten in Journal of fusion energy Springer US, 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)130512575 (DE-600)764392-5 (DE-576)016085973 0164-0313 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 33.00 VZ AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)OLC2070460894 (DE-He213)s10894-014-9736-z-p DE-627 ger DE-627 rakwb eng 530 VZ 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Springer Science+Business Media New York 2014 Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. CFETR Vacuum vessel Electromagnetic analysis Eddy current Plasma major disruption Mechanical analysis Chen, Mingfeng aut Lei, Mingzhun aut Lu, Mingxuan aut Wang, Zhongwei aut Enthalten in Journal of fusion energy Springer US, 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)130512575 (DE-600)764392-5 (DE-576)016085973 0164-0313 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 33.00 VZ AR 33 2014 6 06 07 713-719 |
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Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
| abstract |
Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. © Springer Science+Business Media New York 2014 |
| abstractGer |
Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. © Springer Science+Business Media New York 2014 |
| abstract_unstemmed |
Abstract China Fusion Engineering Test Reactor (CFETR) is a superconducting magnet tokamak and its goal is to achieve the magnetic confinement fusion. The electromagnetic (EM) transients cause mechanical forces, which represent one of the most vital loads for tokamak vacuum vessel (VV). This paper is focused on calculational methods and results for the EM loads on the simplified but practical model of CFETR VV with respect to plasma major disruption scenarios as a reference of the design and analysis. Commercial finite element method software, ANSYS, was employed to evaluate the eddy current on the VV module with the 22.5 ° sector model for major conducting structure of the tokamak including double-walled VV, T-shape rib, and three ports. The plasma current is damping as exponential function 36 ms corresponding to the current simulating in ITER outputs, which are one of major sources of EM loads on VV components. As the results of calculating the eddy currents and EM forces, stress and deformation on CFETR VV can be obtained, which is useful for the structural design of VV. © Springer Science+Business Media New York 2014 |
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| title_short |
Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
| url |
https://doi.org/10.1007/s10894-014-9736-z |
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| author2 |
Chen, Mingfeng Lei, Mingzhun Lu, Mingxuan Wang, Zhongwei |
| author2Str |
Chen, Mingfeng Lei, Mingzhun Lu, Mingxuan Wang, Zhongwei |
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130512575 |
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| doi_str |
10.1007/s10894-014-9736-z |
| up_date |
2024-07-04T01:22:20.716Z |
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7.398694 |