Zobrazeno 1 - 10
of 61
pro vyhledávání: '"V.L. Komarov"'
Autor:
A. Labusov, V. Sorin, Sergey Grigoriev, V. A. Krylov, V. Pyrjaev, G. Dalle Carbonare, G. Saksaganski, V. Bykov, A. Boykov, Victor Tanchuk, V.L. Komarov, Yu. Krasikov
Publikováno v:
Fusion Engineering and Design. :1049-1054
The thermal shield system provides the required reduction of both total and local thermal loads to the cold structures operating at 4.5 K. The most complex thermal shield component is the vacuum vessel (VV) thermal shield (VVTS) located in a narrow g
Publikováno v:
Fusion Engineering and Design. :185-190
Joining of tungsten with copper-based cooling structure and armour geometry optimization are the major aspects in development of the tungsten-armoured plasma facing components (PFC). Fabrication techniques and high heat flux (HHF) tests of tungsten-a
Autor:
V. Divavin, Dennis L. Youchison, V.R. Barabash, C. Ibbott, R. Giniatullin, A. Labusov, V.L. Komarov, A. Makhankov, N. Berkhov, I. Mazul, Victor Tanchuk, J.M. McDonald, Sergey Grigoriev
Publikováno v:
Fusion Engineering and Design. :337-342
The glancing angle of incident power on the target of a tokamak divertor results in doubled and highly peaked heat flux onto adjacent downstream tile in the case of lost of tile event (LOTE). As a result downstream tile has higher probability to fail
Publikováno v:
Fusion Engineering and Design. :803-807
Experience on operation and development of alternative ways for thermal loading simulation for plasma facing components (PFC) tests and other fusion technology experiments are described in the article. These methods are based on a simple heat transfe
Autor:
N Yablokov, Nikolay Litunovsky, I.V. Mazul, V.L. Komarov, A. Makhankov, R Giniatulin, A. Gervash
Publikováno v:
Fusion Engineering and Design. :385-391
One of the most difficult tasks in fusion reactor development is the designing, fabrication and high heat flux testing of actively cooled plasma facing components (PFCs). At present, for the ITER divertor project it is necessary to design and test co
Autor:
A. Vainerman, V.L. Komarov, A. Ganenko, R. K. Zalavutdinov, Nikolay Litunovsky, R.N. Giniyatulin, I.V. Mazul, D. Davydov, A. Gervash, V.T. Fedotov
Publikováno v:
Fusion Engineering and Design. :543-549
One of the main problems for ITER divertor target technology is to provide a reliable joint between Be as armour material and copper alloy heat-sink structure. Such joints are to satisfy numerous requirements. In particular these joints should succes
Autor:
A. Arakelov, A. Gekov, A. Anisimov, A. Makhankov, I. Mazul, A. Popov, A.P Ogorodnikov, I.R Kirillov, V.L. Komarov, V. Yuditskiy, N. Jablokov
Publikováno v:
Fusion Engineering and Design. 42:373-379
Liquid metal heat pipes (HP) possess excellent heat transfer characteristics and are now widely used in space and atomic industries as very attractive fully autonomous devices. However, their application in magnetic field devices is restricted due to
First published in English in 1935, this is a vital and stimulating critical appraisal of contemporary thought in the post-World War One era. Written by a selection of leading Marxist thinkers including Nikolai Bukharin, who would later become one of
Autor:
V. V. Teryaev, R.N. Giniatulin, S.V. Turkulets, V. V. Kharitonov, S.V. Alekseev, V. A. Kurnaev, Yu. V. Chernyatjev, V.M. Baranov, V.L. Komarov, Yu.G. Prokofjev, I. V. Vizgalov, S. K. Dimitrov
Publikováno v:
Journal of Nuclear Materials. :721-725
Autor:
Yu.G. Prokofiev, V.L. Komarov, Burtseva Tatyana A, M. I. Persin, O. K. Chugunov, V.A. Sokolov, I. Mazul, L.P. Zav'jalsky, E. F. Dovguchits, E.I. Trofimchuk, A.A. Mitrofansky
Publikováno v:
Journal of Nuclear Materials. :309-314
Investigation results on the resistance of a number of carbon-based materials under intensive ion, electron and neutron fluxes are presented. Main physico-mechanical characteristics of candidate materials are given. Comparative data on resistance to