Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption

The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet...
Ausführliche Beschreibung

Gespeichert in:

Autor*in:	De Bastiani, Marco [verfasserIn] Bonifetto, Roberto [verfasserIn] Messina, Giuseppe [verfasserIn] Morici, Luigi [verfasserIn] Zanino, Roberto [verfasserIn] Zappatore, Andrea [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2023

Schlagwörter:	Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption

Übergeordnetes Werk:	Enthalten in: Fusion engineering and design - New York, NY [u.a.] : Elsevier, 1987, 196
Übergeordnetes Werk:	volume:196

DOI / URN:	10.1016/j.fusengdes.2023.113987

Katalog-ID:	ELV065271580

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245	1	0	\|a Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
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520			\|a The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD.
650		4	\|a Superconducting magnets
650		4	\|a Nuclear fusion reactors
650		4	\|a Numerical modeling
650		4	\|a Electro-magnetics
650		4	\|a Thermal-hydraulics
650		4	\|a Major plasma disruption
700	1		\|a Bonifetto, Roberto \|e verfasserin \|0 (orcid)0000-0002-3557-9177 \|4 aut
700	1		\|a Messina, Giuseppe \|e verfasserin \|4 aut
700	1		\|a Morici, Luigi \|e verfasserin \|4 aut
700	1		\|a Zanino, Roberto \|e verfasserin \|4 aut
700	1		\|a Zappatore, Andrea \|e verfasserin \|4 aut
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allfields	10.1016/j.fusengdes.2023.113987 doi (DE-627)ELV065271580 (ELSEVIER)S0920-3796(23)00569-0 DE-627 ger DE-627 rda eng 620 530 VZ 33.81 bkl De Bastiani, Marco verfasserin (orcid)0000-0002-6212-1858 aut Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD. Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption Bonifetto, Roberto verfasserin (orcid)0000-0002-3557-9177 aut Messina, Giuseppe verfasserin aut Morici, Luigi verfasserin aut Zanino, Roberto verfasserin aut Zappatore, Andrea verfasserin aut Enthalten in Fusion engineering and design New York, NY [u.a.] : Elsevier, 1987 196 Online-Ressource (DE-627)302722386 (DE-600)1492280-0 (DE-576)120883481 0920-3796 nnns volume:196 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 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_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.81 Kernfusion VZ AR 196
spelling	10.1016/j.fusengdes.2023.113987 doi (DE-627)ELV065271580 (ELSEVIER)S0920-3796(23)00569-0 DE-627 ger DE-627 rda eng 620 530 VZ 33.81 bkl De Bastiani, Marco verfasserin (orcid)0000-0002-6212-1858 aut Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD. Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption Bonifetto, Roberto verfasserin (orcid)0000-0002-3557-9177 aut Messina, Giuseppe verfasserin aut Morici, Luigi verfasserin aut Zanino, Roberto verfasserin aut Zappatore, Andrea verfasserin aut Enthalten in Fusion engineering and design New York, NY [u.a.] : Elsevier, 1987 196 Online-Ressource (DE-627)302722386 (DE-600)1492280-0 (DE-576)120883481 0920-3796 nnns volume:196 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 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_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.81 Kernfusion VZ AR 196
allfields_unstemmed	10.1016/j.fusengdes.2023.113987 doi (DE-627)ELV065271580 (ELSEVIER)S0920-3796(23)00569-0 DE-627 ger DE-627 rda eng 620 530 VZ 33.81 bkl De Bastiani, Marco verfasserin (orcid)0000-0002-6212-1858 aut Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD. Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption Bonifetto, Roberto verfasserin (orcid)0000-0002-3557-9177 aut Messina, Giuseppe verfasserin aut Morici, Luigi verfasserin aut Zanino, Roberto verfasserin aut Zappatore, Andrea verfasserin aut Enthalten in Fusion engineering and design New York, NY [u.a.] : Elsevier, 1987 196 Online-Ressource (DE-627)302722386 (DE-600)1492280-0 (DE-576)120883481 0920-3796 nnns volume:196 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 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_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.81 Kernfusion VZ AR 196
allfieldsGer	10.1016/j.fusengdes.2023.113987 doi (DE-627)ELV065271580 (ELSEVIER)S0920-3796(23)00569-0 DE-627 ger DE-627 rda eng 620 530 VZ 33.81 bkl De Bastiani, Marco verfasserin (orcid)0000-0002-6212-1858 aut Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD. Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption Bonifetto, Roberto verfasserin (orcid)0000-0002-3557-9177 aut Messina, Giuseppe verfasserin aut Morici, Luigi verfasserin aut Zanino, Roberto verfasserin aut Zappatore, Andrea verfasserin aut Enthalten in Fusion engineering and design New York, NY [u.a.] : Elsevier, 1987 196 Online-Ressource (DE-627)302722386 (DE-600)1492280-0 (DE-576)120883481 0920-3796 nnns volume:196 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 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_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.81 Kernfusion VZ AR 196
allfieldsSound	10.1016/j.fusengdes.2023.113987 doi (DE-627)ELV065271580 (ELSEVIER)S0920-3796(23)00569-0 DE-627 ger DE-627 rda eng 620 530 VZ 33.81 bkl De Bastiani, Marco verfasserin (orcid)0000-0002-6212-1858 aut Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD. Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption Bonifetto, Roberto verfasserin (orcid)0000-0002-3557-9177 aut Messina, Giuseppe verfasserin aut Morici, Luigi verfasserin aut Zanino, Roberto verfasserin aut Zappatore, Andrea verfasserin aut Enthalten in Fusion engineering and design New York, NY [u.a.] : Elsevier, 1987 196 Online-Ressource (DE-627)302722386 (DE-600)1492280-0 (DE-576)120883481 0920-3796 nnns volume:196 GBV_USEFLAG_U GBV_ELV SYSFLAG_U GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_65 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_150 GBV_ILN_151 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 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_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 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_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 33.81 Kernfusion VZ AR 196
language	English
source	Enthalten in Fusion engineering and design 196 volume:196
sourceStr	Enthalten in Fusion engineering and design 196 volume:196
format_phy_str_mv	Article
bklname	Kernfusion
institution	findex.gbv.de
topic_facet	Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption
dewey-raw	620
isfreeaccess_bool	false
container_title	Fusion engineering and design
authorswithroles_txt_mv	De Bastiani, Marco @@aut@@ Bonifetto, Roberto @@aut@@ Messina, Giuseppe @@aut@@ Morici, Luigi @@aut@@ Zanino, Roberto @@aut@@ Zappatore, Andrea @@aut@@
publishDateDaySort_date	2023-01-01T00:00:00Z
hierarchy_top_id	302722386
dewey-sort	3620
id	ELV065271580
language_de	englisch
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author	De Bastiani, Marco
spellingShingle	De Bastiani, Marco ddc 620 bkl 33.81 misc Superconducting magnets misc Nuclear fusion reactors misc Numerical modeling misc Electro-magnetics misc Thermal-hydraulics misc Major plasma disruption Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
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topic_title	620 530 VZ 33.81 bkl Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption Superconducting magnets Nuclear fusion reactors Numerical modeling Electro-magnetics Thermal-hydraulics Major plasma disruption
topic	ddc 620 bkl 33.81 misc Superconducting magnets misc Nuclear fusion reactors misc Numerical modeling misc Electro-magnetics misc Thermal-hydraulics misc Major plasma disruption
topic_unstemmed	ddc 620 bkl 33.81 misc Superconducting magnets misc Nuclear fusion reactors misc Numerical modeling misc Electro-magnetics misc Thermal-hydraulics misc Major plasma disruption
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title	Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
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title_full	Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
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author_browse	De Bastiani, Marco Bonifetto, Roberto Messina, Giuseppe Morici, Luigi Zanino, Roberto Zappatore, Andrea
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title_sort	electro dynamic model of eddy currents in eu demo tf coil casing during major plasma disruption
title_auth	Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
abstract	The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD.
abstractGer	The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD.
abstract_unstemmed	The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion consortium. Many different fault transients must be considered and carefully analyzed in the design phase; one of the most severe is the major plasma disruption (MPD), which causes several drawbacks on the magnet system. During a disruption, the plasma current decreases extremely fast, causing a fast variation of the magnetic field, which in turn induces an electric field. In presence of conductive materials, e.g., coil casing and vacuum vessel (VV), the electric field induces large eddy currents which deposit power by Joule effect. The conductive regions are tightly coupled on different timescales through the magnetic field induced by the eddy currents: the eddy currents in the VV influence the magnetic field evolution in the TF coil casing, thus affecting the power deposition in the latter. The aim of this work is the evaluation of the power deposited within the TF coil casing during a major plasma disruption due to eddy currents. The power deposition has been evaluated by means of the 3D-FOX, a finite element (FE) tool developed at Politecnico di Torino. The computed power deposition is used as input to the thermal-hydraulic (TH) simulation, performed with the 4C code, with the aim of assessing the erosion of the temperature margin given by MPD.
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title_short	Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption
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author2	Bonifetto, Roberto Messina, Giuseppe Morici, Luigi Zanino, Roberto Zappatore, Andrea
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up_date	2024-07-06T22:26:44.299Z
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Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption

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