The scan of ion cyclotron resonant heating (ICRH) power has been used to systematically study the pump out effect of central electron heating on impurities such as Ni and Mo in H-mode low collisionality discharges in JET. The transport parameters of Ni and Mo have been measured by introducing a transient perturbation on their densities via the laser blow off technique. Without ICRH Ni and Mo density profiles are typically peaked. The application of ICRH induces on Ni and Mo in the plasma centre (at normalized poloidal flux rho = 0.2) an outward drift approximately proportional to the amount of injected power. Above a threshold of ICRH power of about 3 MW in the specific case the radial flow of Ni and Mo changes from inwards to outwards and the impurity profiles, extrapolated to stationary conditions, become hollow. At mid-radius the impurity profiles become flat or only slightly hollow. In the plasma centre the variation of the convection-to-diffusivity ratio upsilon/D of Ni is particularly well correlated with the change in the ion temperature gradient in qualitative agreement with the neoclassical theory. However, the experimental radial velocity is larger than the neoclassical one by up to one order of magnitude. Gyrokinetic simulations of the radial impurity fluxes induced by electrostatic turbulence do not foresee a flow reversal in the analysed discharges.

Metal impurity transport control in JET H-mode plasmas with central ion cyclotron radiofrequency power injection

M Valisa;L Carraro;I Predebon;ME Puiatti;P Mantica;
2011

Abstract

The scan of ion cyclotron resonant heating (ICRH) power has been used to systematically study the pump out effect of central electron heating on impurities such as Ni and Mo in H-mode low collisionality discharges in JET. The transport parameters of Ni and Mo have been measured by introducing a transient perturbation on their densities via the laser blow off technique. Without ICRH Ni and Mo density profiles are typically peaked. The application of ICRH induces on Ni and Mo in the plasma centre (at normalized poloidal flux rho = 0.2) an outward drift approximately proportional to the amount of injected power. Above a threshold of ICRH power of about 3 MW in the specific case the radial flow of Ni and Mo changes from inwards to outwards and the impurity profiles, extrapolated to stationary conditions, become hollow. At mid-radius the impurity profiles become flat or only slightly hollow. In the plasma centre the variation of the convection-to-diffusivity ratio upsilon/D of Ni is particularly well correlated with the change in the ion temperature gradient in qualitative agreement with the neoclassical theory. However, the experimental radial velocity is larger than the neoclassical one by up to one order of magnitude. Gyrokinetic simulations of the radial impurity fluxes induced by electrostatic turbulence do not foresee a flow reversal in the analysed discharges.
2011
Istituto di fisica del plasma - IFP - Sede Milano
Istituto gas ionizzati - IGI - Sede Padova
Inglese
51
3
033002
11
http://iopscience.iop.org/0029-5515/51/3/033002/
Sì, ma tipo non specificato
FUSION DEVICES
ASDEX UPGRADE
NM REGION
CONFINEMENT
TOKAMAK
This work was supported by EURATOM and carried out within the framework of the European Fusion Development Agreement "Funding under Association Contract FU07-CT-2007-00053". / Article Number: 033002./ La rivista è pubblicata anche online con ISSN 1741-4326, Editore: Institute of Physics Publishing (IOP) Bristol, GB.
20
info:eu-repo/semantics/article
262
Valisa, M; Carraro, L; Predebon, I; Puiatti, Me; Angioni, C; Coffey, I; Giroud, C; Lauro Taroni, L; Alper, B; Baruzzo, M; Belo daSilva, P; Buratti, P;...espandi
01 Contributo su Rivista::01.01 Articolo in rivista
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   EU Fusion for ITER Applications
   EUFORIA
   FP7
   211804
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/144532
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