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Dive into the research topics where F. Nespoli is active.

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Featured researches published by F. Nespoli.


Physics of Plasmas | 2017

Poloidal asymmetry in the narrow heat flux feature in the TCV scrape-off layer

C.K. Tsui; J.A. Boedo; Federico David Halpern; Joaquim Loizu; F. Nespoli; J. Horacek; B. Labit; J. Morales; H. Reimerdes; Paolo Ricci; C. Theiler; S. Coda; B.P. Duval; I. Furno; Tcv Team; EUROfusion Mst Team

Heat flux profiles inferred from a reciprocating probe at the outer midplane of the TCV tokamak during inner wall limited discharges feature radial fall-off lengths that shorten near the last closed flux surface (LCFS) consistent with the so-called narrow feature. The narrow feature is significantly wider on the outboard side compared with that measured on the inner wall by infrared thermography, so it is difficult to discern from the main scrape-off layer feature. After small shifts were applied for alignment, the fraction of the power contained in the narrow feature matches between inboard and outboard measurements, and they scale together with plasma current Ip, suggesting that we are observing the same phenomenon. The outboard side fall-off length within the narrow feature is found to scale closely with the radial correlation length of the edge turbulence as expected if the narrow feature arises due to radially sheared E × B flows. This is found to hold true even for cases where the narrow feature is ...


Physics of Plasmas | 2018

Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas

F. Nespoli; B. Labit; I. Furno; C. Theiler; U. Sheikh; C.K. Tsui; J.A. Boedo; Tcv Team

In inboard-limited plasmas, foreseen to be used in future fusion reactor start-up and ramp down phases, the Scrape-Off Layer (SOL) exhibits two regions: the “near” and “far” SOL. The steep radial gradient of the parallel heat flux associated with the near SOL can result in excessive thermal loads onto the solid surfaces, damaging them and/or limiting the operational space of a fusion reactor. In this article, leveraging the results presented in the study by F. Nespoli et al. [Nucl. Fusion 57, 126029 (2017)], we propose a technique for the mitigation and suppression of the near SOL heat flux feature by impurity seeding. The first successful experimental results from the TCV tokamak are presented and discussed.


Physics of Plasmas | 2018

Filamentary velocity scaling validation in the TCV tokamak

C.K. Tsui; J.A. Boedo; J. R. Myra; B.P. Duval; B. Labit; C. Theiler; N. Vianello; W. A. J. Vijvers; H. Reimerdes; S. Coda; O. Février; J. Harrison; J. Horacek; B. Lipschultz; R. Maurizio; F. Nespoli; U. Sheikh; K. Verhaegh; N. Walkden; Tcv Team; EUROfusion Mst Team

A large database of reciprocating probe data from the edge plasma of TCV (Tokamak a Configuration Variable) is used to test the radial velocity scalings of filaments from analytical theory [Myra et al., Phys. Plasmas 13, 112502 (2006)]. The measured velocities are mainly scattered between zero and a maximum velocity which varies as a function of size and collisionality in agreement with the analytical scalings. The scatter is consistent with mechanisms that tend to slow the velocity of individual filaments. While the radial velocities were mainly clustered between 0.5 and 2 km/s, a minority reached outward velocities as high as 5 km/s or inward velocities as high as −4 km/s. Inward moving filaments are only observed in regions of high poloidal velocity shear in discharges with B × ∇B away from the X-point, a new finding. The filaments have diameters clustered between 3 and 11 mm, and normalized sizes a clustered between 0.3 and 1.1, such that most filaments populate the resistive-ballooning regime; therefore, most of the filaments in TCV have radial velocities with little or no dependence on collisionality. Improvements in cross-correlation techniques and conditional averaging techniques are discussed which reduce the sizes determined for the largest filaments, including those larger than the scrape-off layer.A large database of reciprocating probe data from the edge plasma of TCV (Tokamak a Configuration Variable) is used to test the radial velocity scalings of filaments from analytical theory [Myra et al., Phys. Plasmas 13, 112502 (2006)]. The measured velocities are mainly scattered between zero and a maximum velocity which varies as a function of size and collisionality in agreement with the analytical scalings. The scatter is consistent with mechanisms that tend to slow the velocity of individual filaments. While the radial velocities were mainly clustered between 0.5 and 2 km/s, a minority reached outward velocities as high as 5 km/s or inward velocities as high as −4 km/s. Inward moving filaments are only observed in regions of high poloidal velocity shear in discharges with B × ∇B away from the X-point, a new finding. The filaments have diameters clustered between 3 and 11 mm, and normalized ...


Nuclear Fusion | 2015

Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

M. Kocan; R.A. Pitts; G. Arnoux; I. Balboa; P. de Vries; R. Dejarnac; I. Furno; R.J. Goldston; Y. Gribov; J. Horacek; M. Komm; B. Labit; B. LaBombard; C.J. Lasnier; R. Mitteau; F. Nespoli; D. C. Pace; R. Panek; P.C. Stangeby; J. L. Terry; C. Tsui; P. Vondracek


Nuclear Fusion | 2017

Results from recent detachment experiments in alternative divertor configurations on TCV

C. Theiler; B. Lipschultz; J. Harrison; B. Labit; H. Reimerdes; C.K. Tsui; W.A.J. Vijvers; J.A. Boedo; B.P. Duval; S. Elmore; P. Innocente; U. Kruezi; T. Lunt; R. Maurizio; F. Nespoli; U. Sheikh; A. Thornton; S.H.M. van Limpt; K. Verhaegh; N. Vianello; Tcv Team; EUROfusion Mst Team


Journal of Nuclear Materials | 2015

Heat loads in inboard limited L-mode plasmas in TCV

F. Nespoli; B. Labit; I. Furno; G. P. Canal; A. Fasoli


Nuclear materials and energy | 2017

Spectroscopic investigations of divertor detachment in TCV

K. Verhaegh; B. Lipschultz; B.P. Duval; J. Harrison; H. Reimerdes; C. Theiler; B. Labit; R. Maurizio; C. Marini; F. Nespoli; U. Sheikh; C.K. Tsui; N. Vianello; W.A.J. Vijvers


Nuclear materials and energy | 2017

Effect of plasma geometry on divertor heat flux spreading: MONALISA simulations and experimental results from TCV

A. Gallo; Nicolas Fedorczak; R. Maurizio; C. Theiler; S. Elmore; B. Labit; H. Reimerdes; F. Nespoli; P. Ghendrih; T. Eich


Nuclear Fusion | 2017

Understanding and suppressing the near scrape-off layer heat flux feature in inboard-limited plasmas in TCV

F. Nespoli; B. Labit; I. Furno; J. Horacek; C.K. Tsui; J.A. Boedo; R. Maurizio; H. Reimerdes; C. Theiler; Paolo Ricci; Federico David Halpern; U. Sheikh; K. Verhaegh; R.A. Pitts; F. Militello


Plasma Physics and Controlled Fusion | 2017

Blob properties in full-turbulence simulations of the TCV Scrape-Off Layer

F. Nespoli; I. Furno; B. Labit; Paolo Ricci; Fabio Avino; Federico David Halpern; Felix Musil; Fabio Riva

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B. Labit

École Polytechnique Fédérale de Lausanne

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H. Reimerdes

École Polytechnique Fédérale de Lausanne

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C. Theiler

Massachusetts Institute of Technology

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I. Furno

École Polytechnique Fédérale de Lausanne

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R. Maurizio

École Polytechnique Fédérale de Lausanne

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B.P. Duval

École Polytechnique Fédérale de Lausanne

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U. Sheikh

École Polytechnique Fédérale de Lausanne

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K. Verhaegh

École Polytechnique Fédérale de Lausanne

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Federico David Halpern

École Polytechnique Fédérale de Lausanne

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Paolo Ricci

École Polytechnique Fédérale de Lausanne

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