Zobrazeno 1 - 10
of 107
pro vyhledávání: '"I.R Kirillov"'
Autor:
P.I. Kostichev, I.I. Poddubnyi, V. G. Sviridov, I. A. Belyaev, D.M. Obukhov, N. G. Razuvanov, I.R. Kirillov
Publikováno v:
Fusion Engineering and Design. 127:226-233
The effects specific for downward and upward flows of liquid metal (LM) in a vertical rectangular duct in a coplanar magnetic field (MF) are investigated. The experiments were performed in the JIHT's test facility with a closed magnetohydrodynamic (M
Autor:
K.A. Komov, I.R. Kirillov, A.V. Pugachev, I.Yu. Rodin, D.A. Pertsev, E. R. Zapretilina, D.M. Obukhov, O. A. Kovalchuk, A.Yu. Hon, A.A. Lancetov
Publikováno v:
Fusion Engineering and Design. 124:832-836
This paper gives an overview of the new facility for MHD and heat transfer (HT) tests of liquid metal breeder blanket mock-ups in high magnetic field. The facility named LIMITEF5 is under construction now in JSC “NIIEFA” (D.V. Efremov Institute).
Autor:
S.N. Tomilov, Y. Strebkov, I.R. Kirillov, M.N. Sviridenko, I.V. Vitkovsky, A.Yu. Leshukov, V.G. Kovalenko, A.V. Razmerov, D.A. Pertsev, D.M. Obukhov
Publikováno v:
Fusion Engineering and Design. :521-531
This paper gives the results of design development, analysis and RD (2) tritium-breeding zone design for the TBM casing new dimensions (including its optimization to minimize the MHD-pressure drop in lead-lithium coolant and to increase the tritium g
Autor:
D.M. Obukhov, I.R. Kirillov, V. G. Sviridov, L. G. Genin, V. M. Batenin, N. Yu. Pyatnitskaya, I. A. Belyaev, N. G. Razuvanov, I.I. Poddubnyi
Publikováno v:
Fusion Engineering and Design. 104:1-8
This article investigates an effect which was found out in downward flow of liquid metal (LM) in vertical rectangular duct in coplanar magnetic field (MF). The experiments have been performed on facility which located in JIHT. This facility is magnet
Publikováno v:
Fusion Engineering and Design. 91:44-51
Experiments were performed with Test-section of LLCB TBM on NaK. Test-section made of stainless steel (SS) included inlet pipe, inlet collector of rectangular cross section, two rows of parallel poloidal (vertical) ducts and outer collector with outl
Publikováno v:
Fusion Engineering and Design. 89:1421-1425
Breeding zone optimization and choice of testing parameters in support of Indian conceptual design of lead-lithium ceramic breeder test blanket module for ITER are presented. Test matrix in ITER was estimated with regard to lead-lithium flow rate and
Autor:
Y. Strebkov, V.G. Kovalenko, D.M. Obukhov, I.R. Kirillov, V.K. Kapyshev, A.Yu. Leshukov, I.A. Kartashev, A.V. Razmerov, I.V. Vitkovskiy, M.N. Sviridenko, D.A. Pertsev
Publikováno v:
Fusion Engineering and Design. 89:1232-1240
The activity on the design, analysis, and RD – thermal analysis (in both stationary and transient approaches) of TBM design options (four variations of helium and eutectic flowing directions); – structural analysis of TBM design elements for Indu
Autor:
V.K. Kapyshev, D.M. Obukhov, I.R. Kirillov, M.N. Sviridenko, I.A. Kartashev, I.V. Vitovskiy, A.Yu. Leshukov, V.G. Kovalenko, A.V. Razmerov, Y. Strebkov, D.A. Pertsev
Publikováno v:
Fusion Engineering and Design. 87:1487-1494
According to the Technical program of cooperation between the leading research institutes of India and Russian Federation the joint development of lead-lithium ceramic breeder (LLCB) test blanket module (TBM) is one of preferential directions in this
Autor:
I.R. Kirillov, D.A. Pertsev
Publikováno v:
Fusion Engineering and Design. 85:1054-1058
Lead lithium ceramic breeder (LLCB) test blanket module (TBM) was proposed by Indian TBM team for ITER tests. It uses lead lithium eutectic alloy for tritium production and cooling, and ceramic breeder to enhance the tritium production rate (TPR). Th
Autor:
N.N. Vasiliev, V. A. Belyakov, E.N. Bondarchuk, A.A. Borisov, Yu.S. Strebkov, I.R. Kirillov, V.M. Leonov, G.E. Shatalov, B.N. Kolbasov, Yu.A. Sokolov
Publikováno v:
Fusion Engineering and Design. 83:870-876
Conceptual design studies for a tokamak-based demonstration fusion reactor have been carried out in Russia since 1991. The preferred concept was a steady-state operating tokamak with superconducting magnets, a single-null divertor configuration and a