The DTT device: Poloidal field coil assessment for alternative plasma configurations
This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabi...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Ambrosino, R. [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2017 |
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| Schlagwörter: |
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| Umfang: |
11 |
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| Übergeordnetes Werk: |
Enthalten in: CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current - Yang, Qi ELSEVIER, 2021, an international journal for fusion energy and technology devoted to experiments, theory, methods, and design, New York, NY [u.a.] |
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| Übergeordnetes Werk: |
volume:122 ; year:2017 ; pages:322-332 ; extent:11 |
| Links: |
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| DOI / URN: |
10.1016/j.fusengdes.2017.01.055 |
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ELV041322355 |
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| 520 | |a This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. | ||
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| 650 | 7 | |a Alternative divertor concepts |2 Elsevier | |
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| 700 | 1 | |a de Magistris, M. |4 oth | |
| 700 | 1 | |a Minucci, S. |4 oth | |
| 700 | 1 | |a Ramogida, G. |4 oth | |
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10.1016/j.fusengdes.2017.01.055 doi GBV00000000000058A.pica (DE-627)ELV041322355 (ELSEVIER)S0920-3796(17)30075-3 DE-627 ger DE-627 rakwb eng 620 530 620 DE-600 530 DE-600 690 VZ 50.92 bkl Ambrosino, R. verfasserin aut The DTT device: Poloidal field coil assessment for alternative plasma configurations 2017 11 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. Tokamak Elsevier Plasma magnetic configurations Elsevier Alternative divertor concepts Elsevier Albanese, R. oth Calabrò, G. oth Castaldo, A. oth Crisanti, F. oth Loschiavo, V.P. oth de Magistris, M. oth Minucci, S. oth Ramogida, G. oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:122 year:2017 pages:322-332 extent:11 https://doi.org/10.1016/j.fusengdes.2017.01.055 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 122 2017 322-332 11 045F 620 |
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10.1016/j.fusengdes.2017.01.055 doi GBV00000000000058A.pica (DE-627)ELV041322355 (ELSEVIER)S0920-3796(17)30075-3 DE-627 ger DE-627 rakwb eng 620 530 620 DE-600 530 DE-600 690 VZ 50.92 bkl Ambrosino, R. verfasserin aut The DTT device: Poloidal field coil assessment for alternative plasma configurations 2017 11 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. Tokamak Elsevier Plasma magnetic configurations Elsevier Alternative divertor concepts Elsevier Albanese, R. oth Calabrò, G. oth Castaldo, A. oth Crisanti, F. oth Loschiavo, V.P. oth de Magistris, M. oth Minucci, S. oth Ramogida, G. oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:122 year:2017 pages:322-332 extent:11 https://doi.org/10.1016/j.fusengdes.2017.01.055 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 122 2017 322-332 11 045F 620 |
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10.1016/j.fusengdes.2017.01.055 doi GBV00000000000058A.pica (DE-627)ELV041322355 (ELSEVIER)S0920-3796(17)30075-3 DE-627 ger DE-627 rakwb eng 620 530 620 DE-600 530 DE-600 690 VZ 50.92 bkl Ambrosino, R. verfasserin aut The DTT device: Poloidal field coil assessment for alternative plasma configurations 2017 11 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. Tokamak Elsevier Plasma magnetic configurations Elsevier Alternative divertor concepts Elsevier Albanese, R. oth Calabrò, G. oth Castaldo, A. oth Crisanti, F. oth Loschiavo, V.P. oth de Magistris, M. oth Minucci, S. oth Ramogida, G. oth Enthalten in Elsevier Yang, Qi ELSEVIER CFD modelling of local scour around Tri-USAF in sand with different arrangements under steady current 2021 an international journal for fusion energy and technology devoted to experiments, theory, methods, and design New York, NY [u.a.] (DE-627)ELV006449069 volume:122 year:2017 pages:322-332 extent:11 https://doi.org/10.1016/j.fusengdes.2017.01.055 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U 50.92 Meerestechnik VZ AR 122 2017 322-332 11 045F 620 |
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This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. |
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This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. |
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This paper firstly illustrates the objectives, the figure of merits and the specifications considered in the design of the equilibrium configurations in the Divertor Tokamak Test (DTT) facility. The reference single null scenario is detailed. The range of alternative plasma shapes and current capabilities are then discussed. A number of in-vessel coils can be used to locally modify the magnetic configuration in the divertor region. Finally, a comparison of costs and benefits of the various configurations is given, with particular reference to the power exhaust issues. |
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The DTT device: Poloidal field coil assessment for alternative plasma configurations |
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https://doi.org/10.1016/j.fusengdes.2017.01.055 |
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Albanese, R. Calabrò, G. Castaldo, A. Crisanti, F. Loschiavo, V.P. de Magistris, M. Minucci, S. Ramogida, G. |
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Albanese, R. Calabrò, G. Castaldo, A. Crisanti, F. Loschiavo, V.P. de Magistris, M. Minucci, S. Ramogida, G. |
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ELV006449069 |
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| doi_str |
10.1016/j.fusengdes.2017.01.055 |
| up_date |
2024-07-06T19:48:35.765Z |
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1803860381024649216 |
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