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Enhanced integrators for WEST magnetic diagnostics.

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Title: Enhanced integrators for WEST magnetic diagnostics.
Authors: Spuig, Pascal1 pascal.spuig@cea.fr, Kumari, Praveena2, Moreau, Michel1, Moreau, Philippe1, Le-luyer, Alain1, Malard, Philippe1
Source: Fusion Engineering & Design. Oct2015, Vol. 96/97, p966-969. 4p.
Subjects: Tokamaks, Magnetic fields, Fusion reactor divertors, Plasma diagnostics, Integrators, Magnetic measurements
Abstract: The WEST project consists of implementing a divertor configuration in the Tore Supra Tokamak. This modification requires to renew the magnetic diagnostics and especially adding new magnetic sensors in the divertor region. This has provided an opportunity to consider some enhancements to the existing integrator modules of the magnetic diagnostics. Two prototypes have been produced using different combinations of technical solutions, aiming to achieve lower drift and higher common mode rejection ratio (CMRR). This paper presents the explored and tested ways we followed in order to create enhanced analogue integrators for long pulses. The results of extensive and comprehensive tests are summarized. The achieved performances are analyzed regarding the WEST project specifications and furthermore, the latest ITER requirements for magnetic diagnostics integrators are also considered. [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.)
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DbLabel: Engineering Source
An: 109980610
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PubType: Academic Journal
PubTypeId: academicJournal
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  Data: <searchLink fieldCode="DE" term="%22Tokamaks%22">Tokamaks</searchLink><br /><searchLink fieldCode="DE" term="%22Magnetic+fields%22">Magnetic fields</searchLink><br /><searchLink fieldCode="DE" term="%22Fusion+reactor+divertors%22">Fusion reactor divertors</searchLink><br /><searchLink fieldCode="DE" term="%22Plasma+diagnostics%22">Plasma diagnostics</searchLink><br /><searchLink fieldCode="DE" term="%22Integrators%22">Integrators</searchLink><br /><searchLink fieldCode="DE" term="%22Magnetic+measurements%22">Magnetic measurements</searchLink>
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  Data: The WEST project consists of implementing a divertor configuration in the Tore Supra Tokamak. This modification requires to renew the magnetic diagnostics and especially adding new magnetic sensors in the divertor region. This has provided an opportunity to consider some enhancements to the existing integrator modules of the magnetic diagnostics. Two prototypes have been produced using different combinations of technical solutions, aiming to achieve lower drift and higher common mode rejection ratio (CMRR). This paper presents the explored and tested ways we followed in order to create enhanced analogue integrators for long pulses. The results of extensive and comprehensive tests are summarized. The achieved performances are analyzed regarding the WEST project specifications and furthermore, the latest ITER requirements for magnetic diagnostics integrators are also considered. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
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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.2015.06.047
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      – Code: eng
        Text: English
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        Type: general
      – SubjectFull: Magnetic fields
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      – SubjectFull: Fusion reactor divertors
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      – SubjectFull: Plasma diagnostics
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              Text: Oct2015
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