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(EXP5/17) Regimes with Sharp Density Profile and Enhanced Energy Confinement under Deuterium Pellet Injection and ECRH in T-10

Yu. D. Pavlov, Yu. Dnestrovskij, A. A. Borshegovskij, V. V. Chistiakov, A. V. Gorshkov, Yu. V. Gott, N. V. Ivanov, A. M. Kakurin, L. Khimchenko, A. V. Khramenkov, N. Kirneva, S. V. Krylov, V. A. Krupin, V. V. Matveev, T. B. Mialton, A. Yu. Novikov, V. V. Piterskij, S. V. Popovichev, V. V. Prut, I. N. Roy, M. B. Safonova, V. V. Sannikov, S. A. Shibaev, A. Sushkov, V. Trukhin, V. V. Volkov, V. Zaveriaev
 
Nuclear Fusion Institute, Russian Research Center ``Kurchatov Institute'', Moscow, Russia

Abstract.  Experiments with deuterium pellet injection have been carried out on T-10. The main plasma parameters are as follows: I_p $\approx$ 250 - 300kA, n_e $\approx$ (3 - 4)×10¹³cm^{- 3}, P_ECRH $\approx$ 400 - 700kW. A deuterium pellet was injected into the plasma at the stage of auxiliary ECRH. The main results are as follows: (a) a rapid sharpening of the plasma density profile with the increase of n_e(0) after pellet injection and the sustainment of this profile during the whole ECRH pulse while the averaged chord density remained constant; (b) the lowering of Z_eff(0) and the redistribution of Z_eff(r); (c) the growth of ion temperature ; (d) the increase of plasma energy content and of energy confinement time $\tau_{\mathrm{E}}^{}$ by a factor of $\sim$ 1.5 as compared to $\tau_{\mathrm{E}}^{}$ before pellet injection. The experimental results obtained are close to the RI-mode in TEXTOR after impurity feeding and can be described by the Canonical Profiles Transport Model.

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