Zobrazeno 1 - 10
of 18
pro vyhledávání: '"I.V. Mozin"'
Autor:
G.V. Trokhachev, B.V. Stepanov, S.I. Novikov, A.G. Plesch, E.N. Bondarchuk, G. I. Kiknadze, A.G. Roshal, S.V. Krasnov, N.A. Chernoplekov, E.Y. Klimenko, M.V. Zhelamsky, S.S. Repin, V.G. Yakubovsky, I. K. Butkevich, A. N. Safronov, V.V. Kalinin, O.G. Filatov, I.V. Mozin, V.G. Ivkin, Y. Krivchenkov
Publikováno v:
IEEE Transactions on Magnetics. 28:593-596
The existing SIMS facility built in the Kurchatov Institute for testing the Tokamak T-15 toroidal coils is being reconstructed into an upgrading SIMS-2 facility for the ITER (International Thermonuclear Experimental Reactor) model pancakes. This faci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5973eece1064eb06219ffbcfd543ea33
https://doi.org/10.1109/20.119946
https://doi.org/10.1109/20.119946
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 352:176-178
A computer-aided system is developed for the more effective choice and optimization of the design and manufacturing technologies of the superconductor for the magnet system of the International Thermonuclear Experimental Reactor (ITER) with the aim t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::168991afae517d69d65005c535490c8d
https://doi.org/10.1016/0168-9002(94)91492-3
https://doi.org/10.1016/0168-9002(94)91492-3
Autor:
D. P. Ivanov, P.P. Khvostenko, I.V. Mozin, V. D. Kovalenko, B. A. Stavissky, S.G. Filatov, G. M. Kashirskikh, V. S. Strelkov, N.A. Monoszon, A.N. Vertiporokh, G.F. Churakov, N.A. Chernoplekov, V. G. Motenko, G.E. Notkin, L.B. Dinaburg, I.A. Posadsky, I. K. Butkevich, N.N. Britousov, G.V. Trokhachev
Results of the experiments on cooling, cryostatting, current tests and on Ohmic plasma heating at T-15 facility using the largest (at present) superconducting magnetic system with the current-carrying element based on Nb3Sn are given in the paper.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c431529e33325fdef9b2cf77f87e3e2a
https://doi.org/10.1016/b978-0-444-88508-1.50103-1
https://doi.org/10.1016/b978-0-444-88508-1.50103-1
Publisher Summary This chapter describes the plasma equilibrium control concept on a T-15 facility. Control is hierarchical and is realized on three levels: (1) calculation of control programs for rather long-term series of experiments, (2) correctio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f195c587514e7091c5d8c6ac0ad9276
https://doi.org/10.1016/b978-0-444-88508-1.50066-9
https://doi.org/10.1016/b978-0-444-88508-1.50066-9
Autor:
B. G. Karasev, E. V. Seredenko, I.V. Mozin, V.P. Muratov, R.L. Litunovsky, L.B. Dinaburg, B.B. Kadomtsev, G.V. Trohachev, L. A. Matalin-slutsky, V.G. Ivkin, N.N. Britousov, A.I. Kostenlco, A.N. Volobuev, I.M. Samoilov, V. I. Peregud, B.A. Stavissky, V.V. Spirchenko, E.V. Kornakov, E.O. Adamov, S.N. Sadakov, G.F. Churakov, N.V. Krasnov, V. A. Glukhikh, V. S. Strelkov, E.P. Velikhov, N.N. Semachko, S.P. Gurin, V. V. Alikaev, I.F. Malyshev, N.A. Monoszon, D. P. Ivanov, N.A. Chernoplekov
Tokamak T-15 installation, being constructed in I.V. Kurchatov institute (IAE) is In common with the large installations JET, TFTR, JT-60, TORE SUPRA, aimed to get and investidate fusion parameter plasma and to solve some engineering problems, associ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b7ce271128c2676937ed37d1cdcef7c4
https://doi.org/10.1016/b978-1-4832-8376-0.50084-x
https://doi.org/10.1016/b978-1-4832-8376-0.50084-x
Autor:
P.P. Teplov, I.V. Mozin, V. P. Smirnov, R.N. Litunovsky, A.V. Kuznetsov, V.G. Ivkin, V.A. Belyakov, A.M. Stolov
The T-15 poloidal field control system is designed on the basis of experimental investigations, made on the Tokamak “Tuman-3” and numerical modeling data. The purpose of the calculations is to investigate the plasma position and current control s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7eedb29eee9a5f3b0e3d1c14f62e148f
https://doi.org/10.1016/b978-1-4832-8374-6.50178-7
https://doi.org/10.1016/b978-1-4832-8374-6.50178-7
Autor:
V.I. Vasil'ev, Yu. Gribov, B.A. Alekseev, V.L. Savikovsky, P.P. Teplov, B.A. Belyakov, Yu.A. Kostsov, R.N. Litunovsky, I.V. Mozin, V. Chuyanov, V.N. Minyaev
A high-magnetic field tokamak is designed for plasma heating experiments by adiabatic compression of plasma over major and minor radii. Neutral beam injection heating is used as well. The plasma position and current control system includes a diagnost
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b878d8d2586de6cc1876a9ffb5e5320
https://doi.org/10.1016/b978-1-4832-8374-6.50174-x
https://doi.org/10.1016/b978-1-4832-8374-6.50174-x
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