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...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Liu, Sumei [verfasserIn] Chen, Mingfeng [verfasserIn] Lei, Mingzhun [verfasserIn] Lu, Mingxuan [verfasserIn] Wang, Zhongwei [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2014 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
Enthalten in: Journal of fusion energy - New York, NY : Springer Science + Business Media B.V., 1981, 33(2014), 6 vom: 06. Juli, Seite 713-719 |
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| Übergeordnetes Werk: |
volume:33 ; year:2014 ; number:6 ; day:06 ; month:07 ; pages:713-719 |
| Links: |
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| DOI / URN: |
10.1007/s10894-014-9736-z |
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| Katalog-ID: |
SPR014393654 |
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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. | ||
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| 650 | 4 | |a Electromagnetic analysis |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Eddy current |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Plasma major disruption |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Mechanical analysis |7 (dpeaa)DE-He213 | |
| 700 | 1 | |a Chen, Mingfeng |e verfasserin |4 aut | |
| 700 | 1 | |a Lei, Mingzhun |e verfasserin |4 aut | |
| 700 | 1 | |a Lu, Mingxuan |e verfasserin |4 aut | |
| 700 | 1 | |a Wang, Zhongwei |e verfasserin |4 aut | |
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10.1007/s10894-014-9736-z doi (DE-627)SPR014393654 (SPR)s10894-014-9736-z-e DE-627 ger DE-627 rakwb eng 530 ASE 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 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 (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 Chen, Mingfeng verfasserin aut Lei, Mingzhun verfasserin aut Lu, Mingxuan verfasserin aut Wang, Zhongwei verfasserin aut Enthalten in Journal of fusion energy New York, NY : Springer Science + Business Media B.V., 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)320574636 (DE-600)2016894-9 1572-9591 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://dx.doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.00 ASE AR 33 2014 6 06 07 713-719 |
| spelling |
10.1007/s10894-014-9736-z doi (DE-627)SPR014393654 (SPR)s10894-014-9736-z-e DE-627 ger DE-627 rakwb eng 530 ASE 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 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 (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 Chen, Mingfeng verfasserin aut Lei, Mingzhun verfasserin aut Lu, Mingxuan verfasserin aut Wang, Zhongwei verfasserin aut Enthalten in Journal of fusion energy New York, NY : Springer Science + Business Media B.V., 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)320574636 (DE-600)2016894-9 1572-9591 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://dx.doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.00 ASE AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)SPR014393654 (SPR)s10894-014-9736-z-e DE-627 ger DE-627 rakwb eng 530 ASE 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 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 (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 Chen, Mingfeng verfasserin aut Lei, Mingzhun verfasserin aut Lu, Mingxuan verfasserin aut Wang, Zhongwei verfasserin aut Enthalten in Journal of fusion energy New York, NY : Springer Science + Business Media B.V., 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)320574636 (DE-600)2016894-9 1572-9591 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://dx.doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.00 ASE AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)SPR014393654 (SPR)s10894-014-9736-z-e DE-627 ger DE-627 rakwb eng 530 ASE 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 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 (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 Chen, Mingfeng verfasserin aut Lei, Mingzhun verfasserin aut Lu, Mingxuan verfasserin aut Wang, Zhongwei verfasserin aut Enthalten in Journal of fusion energy New York, NY : Springer Science + Business Media B.V., 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)320574636 (DE-600)2016894-9 1572-9591 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://dx.doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.00 ASE AR 33 2014 6 06 07 713-719 |
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10.1007/s10894-014-9736-z doi (DE-627)SPR014393654 (SPR)s10894-014-9736-z-e DE-627 ger DE-627 rakwb eng 530 ASE 33.00 bkl Liu, Sumei verfasserin aut Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption 2014 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier 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 (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 Chen, Mingfeng verfasserin aut Lei, Mingzhun verfasserin aut Lu, Mingxuan verfasserin aut Wang, Zhongwei verfasserin aut Enthalten in Journal of fusion energy New York, NY : Springer Science + Business Media B.V., 1981 33(2014), 6 vom: 06. Juli, Seite 713-719 (DE-627)320574636 (DE-600)2016894-9 1572-9591 nnns volume:33 year:2014 number:6 day:06 month:07 pages:713-719 https://dx.doi.org/10.1007/s10894-014-9736-z lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2070 GBV_ILN_2086 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2116 GBV_ILN_2118 GBV_ILN_2119 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4246 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.00 ASE AR 33 2014 6 06 07 713-719 |
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Liu, Sumei @@aut@@ Chen, Mingfeng @@aut@@ Lei, Mingzhun @@aut@@ Lu, Mingxuan @@aut@@ Wang, Zhongwei @@aut@@ |
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<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">SPR014393654</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20220111010303.0</controlfield><controlfield tag="007">cr uuu---uuuuu</controlfield><controlfield tag="008">201006s2014 xx |||||o 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1007/s10894-014-9736-z</subfield><subfield code="2">doi</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)SPR014393654</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(SPR)s10894-014-9736-z-e</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">530</subfield><subfield code="q">ASE</subfield></datafield><datafield tag="084" ind1=" " ind2=" "><subfield code="a">33.00</subfield><subfield code="2">bkl</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Liu, Sumei</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2014</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">Computermedien</subfield><subfield code="b">c</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Online-Ressource</subfield><subfield code="b">cr</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="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. 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Liu, Sumei |
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Liu, Sumei ddc 530 bkl 33.00 misc CFETR misc Vacuum vessel misc Electromagnetic analysis misc Eddy current misc Plasma major disruption misc Mechanical analysis Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
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530 ASE 33.00 bkl Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption CFETR (dpeaa)DE-He213 Vacuum vessel (dpeaa)DE-He213 Electromagnetic analysis (dpeaa)DE-He213 Eddy current (dpeaa)DE-He213 Plasma major disruption (dpeaa)DE-He213 Mechanical analysis (dpeaa)DE-He213 |
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ddc 530 bkl 33.00 misc CFETR misc Vacuum vessel misc Electromagnetic analysis misc Eddy current misc Plasma major disruption misc Mechanical analysis |
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ddc 530 bkl 33.00 misc CFETR misc Vacuum vessel misc Electromagnetic analysis misc Eddy current misc Plasma major disruption misc Mechanical analysis |
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Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
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Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
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Liu, Sumei |
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Journal of fusion energy |
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Liu, Sumei Chen, Mingfeng Lei, Mingzhun Lu, Mingxuan Wang, Zhongwei |
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electromagnetic and structural analysis on vacuum vessel for cfetr during plasma major disruption |
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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. |
| 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. |
| 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. |
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6 |
| title_short |
Electromagnetic and Structural Analysis on Vacuum Vessel for CFETR During Plasma Major Disruption |
| url |
https://dx.doi.org/10.1007/s10894-014-9736-z |
| remote_bool |
true |
| author2 |
Chen, Mingfeng Lei, Mingzhun Lu, Mingxuan Wang, Zhongwei |
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Chen, Mingfeng Lei, Mingzhun Lu, Mingxuan Wang, Zhongwei |
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| doi_str |
10.1007/s10894-014-9736-z |
| up_date |
2024-07-04T01:30:54.894Z |
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| score |
7.400653 |