Zobrazeno 1 - 6
of 6
pro vyhledávání: '"S M Sotnikov"'
Autor:
R. R. Khaĭrutdinov, A. A. Ivanov, I. Ya. Shipuk, E. A. Kuznetsov, N. B. Rodionov, A. A. Petrov, V. P. Rodionova, V. G. Petrov, A. V. Krasilnikov, S. M. Sotnikov, V. I. Gudkov, A. G. Trapeznikov, A. G. Alekseev, É. A. Azizov
Publikováno v:
Plasma Physics Reports. 33:883-889
Results are presented from experimental and theoretical studies of the heating of a hydrogen plasma with a lithium admixture at the fundamental ion-cyclotron frequency of hydrogen in the T-11M tokamak. It is found experimentally that the action of RF
Autor:
A. I. Markin, A. A. Ivanov, S. M. Sotnikov, V. I. Gudkov, A. V. Krasilnikov, N. B. Rodionov, V. P. Rodionova, S. Tugarinov, V. G. Petrov, A. M. Belov, V. A. Myslin, A. G. Alekseev, É. A. Azizov
Publikováno v:
Plasma Physics Reports. 32:83-93
Results are presented from investigations of the possibility of heating a hydrogen plasma at the fundamental harmonic of the ion cyclotron frequency in the T-11M tokamak. The fluxes of charge-exchange atoms that escape from the plasma in the radial d
Autor:
V.A. Evtikhin, E A Azizov, S.V. Mirnov, A. S. Prokhorov, V.B. Lazarev, I E Lyublinski, V M Korzhavin, A.V. Vertkov, S M Sotnikov, V M Safronov
Publikováno v:
Plasma Science and Technology. 6:2291-2295
At present the most promising principal solution of the divertor problem appears to be the use of liquid metals and primarily of lithium Capillary-Pore Systems (CPS) as of plasma facing materials. A solid CPS filled with liquid lithium will have a hi
Publikováno v:
Fusion Engineering and Design. 65:455-465
This paper is a review of the experimental investigations of Li-behavior as limiter material in real tokamak. All experiments were performed in tokamak T-11M with main parameters: plasma current, Ip=100 kA; duration of the discharge 0.1 s, toroidal m
Autor:
B.I. Khripunov, A P Chernobai, V.B. Lazarev, V M Korzhavin, A.V. Vertkov, I E Lyublinski, S.V. Mirnov, V.A. Evtikhin, N P Petrova, S M Sotnikov, V.B. Petrov, D.Yu. Prokhorov
Publikováno v:
Plasma Physics and Controlled Fusion. 44:955-977
The ITER project development has shown that considerable difficulties are encountered when already known engineering solutions and materials are used for divertor and divertor plates for tokamaks of such a scale. We offer to use a Li capillary-pore s
Energy removal and MHD performance of lithium capillary-pore systems for divertor target application
Autor:
V.A. Evtikhin, N.I Yezhov, S M Sotnikov, V.B. Petrov, S.V. Mirnov, B.I. Khripunov, A.V. Vertkov, I.E. Lyublinski
Publikováno v:
Fusion Engineering and Design. :195-199
Experimental results of complex studies of lithium capillary-pore systems (CPS) for application as a plasma facing structure in divertor and on the first wall of a fusion reactor are reported. The ability of CPS to accept and to remove high heat flux