Zobrazeno 1 - 10
of 27
pro vyhledávání: '"R.N. Giniyatulin"'
Autor:
V.P. Budaev, S.D. Fedorovich, A.V. Dedov, A.V. Karpov, A.T. Komov, Yu.V. Martynenko, R.N. Giniyatulin, A.N. Makhankov, N.V. Litunovsky, A.P. Sliva, A.Yu. Marchenkov, D.N. Gerasimov, M.K. Gubkin, M.V. Lukashevsky, A.V. Zakharenkov, A.V. Lazukin, G.B. Vasiliev
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100816- (2020)
Mock-ups of the ITER divertor plate are tested with the combination of steady-state plasma and e-beam loads: (1) thermocyclic tests with powerful electron beam load of up to 49 MW/m2 in the e-beam facility; and then (2) subsequent testing in the PLM
Externí odkaz:
https://doaj.org/article/12357a5a61bf4dea94aa347bc63765ce
Autor:
V.P. Budaev, Yu.V. Martynenko, S.A. Grashin, R.N. Giniyatulin, I.I. Arkhipov, A.V. Karpov, P.V. Savrukhin, E.A. Shestakov, R.Yu. Solomatin, L.B. Begrambekov, N.E. Belova, S.D. Fedorovich, L.N. Khimchenko, V.M. Safronov
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 418-422 (2017)
Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions in the T-10 tokamak. Significant melting, formation of small craters and erosion of the tungsten limiter have been observed after ∼400 discharges wit
Externí odkaz:
https://doaj.org/article/4f3b5c322e784ec29234eed0df90c47a
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
Publikováno v:
Fusion Engineering and Design. 46:229-235
Considering beryllium as plasma facing armour this paper presents recent results obtained in Russia. A special process of joining beryllium to a Cu-alloy material structure is described and recent results of thermal cycling tests of such joints are p
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:
Yu.G. Prokofiev, V.R. Barabash, R.N. Giniyatulin, V.K. Korontsevich, D.L. Miloslavsky, V.F. Khorunov, S.A. Fabritsiev, V.L. Komarov, G.L. Saksagansky, I. Mazul
Publikováno v:
Fusion Engineering and Design. 18:151-156
The carbon-based materials CBM-copper, CBM-molybdenum and tungsten-copper types of joining are considered as reference design elements for the ITER reactor divertor plates. The results of the thermocyclic durability tests of the various types of mock
Akademický článek
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Autor:
T.M. Gurieva, V.A. Bykov, I. Mazul, V.R. Barabash, K. Egorov, L.S. Gitarsky, A. Gervash, V.T. Pronyakin, V.L. Komarov, I.L. Strulia, R.N. Giniyatulin, M. D. Korolkov, V.S. Sizenev
At the present time beryllium is considered as the most suitable armour material for the ITER divertor application. Different types of Be-divertor mock-up construction are compared in the report. Two different technologies of beryllium tiles joining
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::749615550a041df15a17458ee7945ee6
https://doi.org/10.1016/b978-0-444-82220-8.50045-5
https://doi.org/10.1016/b978-0-444-82220-8.50045-5
Akademický článek
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Akademický článek
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