Mohamed Ezzat Publications

Mohamed Ezzat Mostafa

PhD Student for Geothermal Energy and Geofluids

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Mailing Address
Mohamed Ezzat Mostafa
Geothermal Energy & Geofluids
Institute of Geophysics

Contact
Phone +41 44 633 4041
Email m.ezzat@erdw.ethz.ch & m.ezzat@mans.edu.eg

Administration
Dominique Ballarin Dolfin
Phone +41 44 632 3465
Email ballarin@ethz.ch

Publications

THESES

1.  Ezzat, M. Advanced neoclassical impurity transport modelling with its experimental comparison for TJ-II , MSc Thesis, 51 pp., 2018. Abstract
The absence of the disruptive instabilities, increasing of the confinement time with the ECRH heating and the steady-state operation make stellarator concept as a competitive candidate for future fusion reactors as the tokamak. Impurity accumulation in the core though is one of the stellarator drawbacks because it dilutes the plasma and increases the radiation losses contributing to the plasma collapse. Neoclassical theory predicts a non-ambipolar transport of different species electrons and ions in stellarators due to magnetic field ripples that are produced by the three-dimensional coils structure. Non-ambipolar transport creates, depending on the collisionality of each species, inward (outward) an ambipolar radial electric field for ion (electron) root regimes. Ion root regime has been predicted for the future stellarator reactor scenarios, which imply very likely impurity accumulation. However, outward transport has been observed during an improved confinement regime so-called \textit{HDH mode} at W7-AS (\textit{K. McCormick 2002}) and the \textit{impurity hole} at LHD (\textit{K. Ida 2009}) but without without satisfactory theoritical explanation. Historically, neoclassical treatment considers only the radial component of the electric field, which is a good approximation for the bulk species, but not for the higher charge species like impurity. Recent approaches have considered the tangential component due to the variation of the electrostatic potential within a flux surface which is more important for high charge impurity (see \[\textit{J. M. {Garc\’ia-Rega\~na} 2013}\] and reference therein). Advanced modelling of this variational part has been done here for TJ-II plasma introducing a parameter which can be measured indirectly. Direct measurement of the variational part is non-trivial and had been carried only for plasma edge (\textit{M. A. Pedrosa 2015}). Here, the indirect measurements cover the whole cross section by constructing the radiation map at two toroidal planes in TJ-II that carried impurity density distribution and in sequence the variational electrostatic part. Linearized impurity-ion collision operator (in \textit{I. Calvo 2018-Arxiv}) had been employed for impurity simulation because it is higher collisional instead of the usual pitch angel scattering operator (in \textit{C. D. Beidler 2011}) for bulk species with low collisions.

show/hide list of publications

THESES

1.  Ezzat, M. Advanced neoclassical impurity transport modelling with its experimental comparison for TJ-II , MSc Thesis, 51 pp., 2018. Abstract
The absence of the disruptive instabilities, increasing of the confinement time with the ECRH heating and the steady-state operation make stellarator concept as a competitive candidate for future fusion reactors as the tokamak. Impurity accumulation in the core though is one of the stellarator drawbacks because it dilutes the plasma and increases the radiation losses contributing to the plasma collapse. Neoclassical theory predicts a non-ambipolar transport of different species electrons and ions in stellarators due to magnetic field ripples that are produced by the three-dimensional coils structure. Non-ambipolar transport creates, depending on the collisionality of each species, inward (outward) an ambipolar radial electric field for ion (electron) root regimes. Ion root regime has been predicted for the future stellarator reactor scenarios, which imply very likely impurity accumulation. However, outward transport has been observed during an improved confinement regime so-called \textit{HDH mode} at W7-AS (\textit{K. McCormick 2002}) and the \textit{impurity hole} at LHD (\textit{K. Ida 2009}) but without without satisfactory theoritical explanation. Historically, neoclassical treatment considers only the radial component of the electric field, which is a good approximation for the bulk species, but not for the higher charge species like impurity. Recent approaches have considered the tangential component due to the variation of the electrostatic potential within a flux surface which is more important for high charge impurity (see \[\textit{J. M. {Garc\’ia-Rega\~na} 2013}\] and reference therein). Advanced modelling of this variational part has been done here for TJ-II plasma introducing a parameter which can be measured indirectly. Direct measurement of the variational part is non-trivial and had been carried only for plasma edge (\textit{M. A. Pedrosa 2015}). Here, the indirect measurements cover the whole cross section by constructing the radiation map at two toroidal planes in TJ-II that carried impurity density distribution and in sequence the variational electrostatic part. Linearized impurity-ion collision operator (in \textit{I. Calvo 2018-Arxiv}) had been employed for impurity simulation because it is higher collisional instead of the usual pitch angel scattering operator (in \textit{C. D. Beidler 2011}) for bulk species with low collisions.