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Modeling of Tungsten Behavior in Plasma of T-10 Tokamak

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Abstract

The results of numerical modeling of impurity concentration profiles of tungsten ions for discharges with ohmic heating (OH) on the T-10 tokamak with W limiter (for Zeff ≈ 1) are described. It is shown that in OH discharges the maximum values of relative concentrations for each tungsten ion state are located on their radii of coronal equilibrium. Fulfillment of coronal equilibrium on the T-10 tokamak makes it possible to determine the full radiation intensity from the total concentration of tungsten ions. The results show that modeling of the Prad(r) profile for tungsten using currently accepted scaling of anomalous transport coefficients of light and moderate impurities for T-10 plasma does not make it possible to obtain complete alignment with the experimental data. The dependences of tungsten radiation intensity profiles on different published data on excitation, ionization, recombination rates, and anomalous transport coefficients are shown in the paper. A conclusion about the value of the anomalous diffusion coefficient and its radial distribution for heavy impurity (tungsten) in OH discharges at the T-10 tokamak is made.

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Correspondence to I. A. Zemtsov.

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Original Russian Text © I.A. Zemtsov, V.A. Krupin, M.R. Nurgaliev, L.A. Klyuchnikov, A.R. Nemets, A.Yu. Dnestrovskij, D.V. Sarychev, 2017, published in Voprosy Atomnoi Nauki i Tekhniki, Seriya: Termoyadernyi Sintez, 2017, Vol. 40, No. 2, pp. 29–35.

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Zemtsov, I.A., Krupin, V.A., Nurgaliev, M.R. et al. Modeling of Tungsten Behavior in Plasma of T-10 Tokamak. Phys. Atom. Nuclei 81, 1042–1047 (2018). https://doi.org/10.1134/S1063778818070165

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  • DOI: https://doi.org/10.1134/S1063778818070165

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