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H-mode scrape-off layer power width in the TCV tokamak.

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Title: H-mode scrape-off layer power width in the TCV tokamak.
Authors: Maurizio, R. (AUTHOR) maurizior@fusion.gat.com, Duval, B.P. (AUTHOR), Labit, B. (AUTHOR), Reimerdes, H. (AUTHOR), Faitsch, M. (AUTHOR), Komm, M. (AUTHOR), Sheikh, U. (AUTHOR), Theiler, C. (AUTHOR), team, the TCV (AUTHOR), team, the EUROfusion MST1 (AUTHOR)
Source: Nuclear Fusion. Feb2021, Vol. 61 Issue 2, p1-6. 6p.
Subjects: Fusion reactor divertors, Fusion reactors, Electron distribution, Electron temperature measurement, Thomson scattering, Electron scattering, Tokamaks
Abstract: Obtaining acceptable conditions at the divertor targets of a next-step fusion experiment based on the tokamak concept is expected to be particularly challenging because of the small predicted value of the plasma power exhaust channel width. An increased confidence in this prediction is important to forestall any power exhaust issue and in developing corresponding divertor solutions. With the present prediction relying on empirical scaling laws based on data from six tokamaks, this letter tests these scaling laws on an additional device, the TCV tokamak. Estimates of the exhaust channel width, λq, based on Thomson scattering measurements of the electron temperature and density profiles, correlate well with outer target infrared thermography. Reasonable agreement with multi-device scaling laws is found only when including both the power crossing the separatrix and the Greenwald density fraction as regression parameters. TCV's λq is 2 to 3 times smaller than in spherical tokamaks for the same value of the poloidal field. The inclusion of TCV data in the scaling laws would, therefore, require the retention of an explicit aspect ratio dependence, with consequences for all other dependencies. [ABSTRACT FROM AUTHOR]
Copyright of Nuclear Fusion is the property of IOP Publishing 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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DbLabel: Engineering Source
An: 149174319
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  Data: H-mode scrape-off layer power width in the TCV tokamak.
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  Data: <searchLink fieldCode="AR" term="%22Maurizio%2C+R%2E%22">Maurizio, R.</searchLink> (AUTHOR)<i> maurizior@fusion.gat.com</i><br /><searchLink fieldCode="AR" term="%22Duval%2C+B%2EP%2E%22">Duval, B.P.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Labit%2C+B%2E%22">Labit, B.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Reimerdes%2C+H%2E%22">Reimerdes, H.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Faitsch%2C+M%2E%22">Faitsch, M.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Komm%2C+M%2E%22">Komm, M.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Sheikh%2C+U%2E%22">Sheikh, U.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Theiler%2C+C%2E%22">Theiler, C.</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22team%2C+the+TCV%22">team, the TCV</searchLink> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22team%2C+the+EUROfusion+MST1%22">team, the EUROfusion MST1</searchLink> (AUTHOR)
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Fusion%22">Nuclear Fusion</searchLink>. Feb2021, Vol. 61 Issue 2, p1-6. 6p.
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  Data: <searchLink fieldCode="DE" term="%22Fusion+reactor+divertors%22">Fusion reactor divertors</searchLink><br /><searchLink fieldCode="DE" term="%22Fusion+reactors%22">Fusion reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Electron+distribution%22">Electron distribution</searchLink><br /><searchLink fieldCode="DE" term="%22Electron+temperature+measurement%22">Electron temperature measurement</searchLink><br /><searchLink fieldCode="DE" term="%22Thomson+scattering%22">Thomson scattering</searchLink><br /><searchLink fieldCode="DE" term="%22Electron+scattering%22">Electron scattering</searchLink><br /><searchLink fieldCode="DE" term="%22Tokamaks%22">Tokamaks</searchLink>
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  Data: Obtaining acceptable conditions at the divertor targets of a next-step fusion experiment based on the tokamak concept is expected to be particularly challenging because of the small predicted value of the plasma power exhaust channel width. An increased confidence in this prediction is important to forestall any power exhaust issue and in developing corresponding divertor solutions. With the present prediction relying on empirical scaling laws based on data from six tokamaks, this letter tests these scaling laws on an additional device, the TCV tokamak. Estimates of the exhaust channel width, λq, based on Thomson scattering measurements of the electron temperature and density profiles, correlate well with outer target infrared thermography. Reasonable agreement with multi-device scaling laws is found only when including both the power crossing the separatrix and the Greenwald density fraction as regression parameters. TCV's λq is 2 to 3 times smaller than in spherical tokamaks for the same value of the poloidal field. The inclusion of TCV data in the scaling laws would, therefore, require the retention of an explicit aspect ratio dependence, with consequences for all other dependencies. [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of Nuclear Fusion is the property of IOP Publishing 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: 10.1088/1741-4326/abd147
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      – Code: eng
        Text: English
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        PageCount: 6
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      – SubjectFull: Fusion reactor divertors
        Type: general
      – SubjectFull: Fusion reactors
        Type: general
      – SubjectFull: Electron distribution
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      – SubjectFull: Electron temperature measurement
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      – SubjectFull: Thomson scattering
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      – SubjectFull: Electron scattering
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      – SubjectFull: Tokamaks
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      – TitleFull: H-mode scrape-off layer power width in the TCV tokamak.
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              Text: Feb2021
              Type: published
              Y: 2021
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