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Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma.

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Title: Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma.
Authors: Cavazzana, Roberto1 roberto.cavazzana@igi.cnr.it, Marsango, Laura2, Peruzzo, Simone1, Zuin, Matteo1, Gnesotto, Francesco2, Marrelli, Lionello1, Spolaore, Monica1, Martines, Emilio1
Source: Fusion Engineering & Design. Nov2018:Part B, Vol. 136, p1209-1213. 5p.
Subjects: Fusion reactor divertors, Reversed field pinches, Electric potential, Lumped elements, Plasma gases
Abstract: Abstract The externally applied loop voltage, required to drive current carrying magnetic configurations, such as tokamaks or reversed field pinches (RFP), can induce currents between the plasma and the surrounding conducting components, such as limiters, divertor sections, stabilizing plates or enclosing stabilizing shells with insulated electrical gaps. An appropriate modeling of this problem can quantify these currents and give constraints for the design of new devices. In this paper a methodology based on lumped element circuit is used to evaluate this problem for the case of in vessel components of the RFX-mod2, which led to a redesign of the electrical connections of plasma facing components. In the new design some parts, having applied potential in the kV range, are still exposed to the weakly ionized scrape off plasma. The process of arc formation between them and their prevention had been experimentally investigated and possible arc suppression strategies identified. [ABSTRACT FROM AUTHOR]
Copyright of Fusion Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
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Header DbId: egs
DbLabel: Engineering Source
An: 132605406
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma.
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  Data: <searchLink fieldCode="AR" term="%22Cavazzana%2C+Roberto%22">Cavazzana, Roberto</searchLink><relatesTo>1</relatesTo><i> roberto.cavazzana@igi.cnr.it</i><br /><searchLink fieldCode="AR" term="%22Marsango%2C+Laura%22">Marsango, Laura</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AR" term="%22Peruzzo%2C+Simone%22">Peruzzo, Simone</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Zuin%2C+Matteo%22">Zuin, Matteo</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Gnesotto%2C+Francesco%22">Gnesotto, Francesco</searchLink><relatesTo>2</relatesTo><br /><searchLink fieldCode="AR" term="%22Marrelli%2C+Lionello%22">Marrelli, Lionello</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Spolaore%2C+Monica%22">Spolaore, Monica</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Martines%2C+Emilio%22">Martines, Emilio</searchLink><relatesTo>1</relatesTo>
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  Data: <searchLink fieldCode="JN" term="%22Fusion+Engineering+%26+Design%22">Fusion Engineering & Design</searchLink>. Nov2018:Part B, Vol. 136, p1209-1213. 5p.
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  Data: <searchLink fieldCode="DE" term="%22Fusion+reactor+divertors%22">Fusion reactor divertors</searchLink><br /><searchLink fieldCode="DE" term="%22Reversed+field+pinches%22">Reversed field pinches</searchLink><br /><searchLink fieldCode="DE" term="%22Electric+potential%22">Electric potential</searchLink><br /><searchLink fieldCode="DE" term="%22Lumped+elements%22">Lumped elements</searchLink><br /><searchLink fieldCode="DE" term="%22Plasma+gases%22">Plasma gases</searchLink>
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  Data: Abstract The externally applied loop voltage, required to drive current carrying magnetic configurations, such as tokamaks or reversed field pinches (RFP), can induce currents between the plasma and the surrounding conducting components, such as limiters, divertor sections, stabilizing plates or enclosing stabilizing shells with insulated electrical gaps. An appropriate modeling of this problem can quantify these currents and give constraints for the design of new devices. In this paper a methodology based on lumped element circuit is used to evaluate this problem for the case of in vessel components of the RFX-mod2, which led to a redesign of the electrical connections of plasma facing components. In the new design some parts, having applied potential in the kV range, are still exposed to the weakly ionized scrape off plasma. The process of arc formation between them and their prevention had been experimentally investigated and possible arc suppression strategies identified. [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of Fusion Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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        Value: 10.1016/j.fusengdes.2018.04.103
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      – Code: eng
        Text: English
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        Type: general
      – SubjectFull: Reversed field pinches
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      – SubjectFull: Electric potential
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              Text: Nov2018:Part B
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              Y: 2018
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