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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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27a31f43ab2151e44bb78816b7f5397e
https://doi.org/10.1016/j.fusengdes.2014.01.006
https://doi.org/10.1016/j.fusengdes.2014.01.006
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c324b0d058000cf06a60b5015461c852
https://doi.org/10.1016/j.fusengdes.2014.04.011
https://doi.org/10.1016/j.fusengdes.2014.04.011
Autor:
A.N. Kalaschnikov, I.V. Danilov, V.G. Kovalenko, V. Kapyshev, A.V. Razmerov, M.N. Sviridenko, Yu.S. Strebkov, N.K. Vladimirova, A.Yu. Leshukov, I.A. Kartashev, E.A. Trusova, V. Poliksha
Publikováno v:
Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. 37:17-26
Демонстрация тритиевой технологии является одной из главных целей разработки и создания экспериментальных модулей бланкета (ЭМБ) для и
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4084301cb9df6bdfc503959aa12936e8
https://doi.org/10.21517/0202-3822-2014-37-2-17-26
https://doi.org/10.21517/0202-3822-2014-37-2-17-26
Autor:
M.N. Sviridenko, V. Kapyshev, Yu.S. Strebkov, V.G. Kovalenko, A.Yu. Leshukov, A.V. Razmerov, S.A. Makarov, I.A. Kartashev, I.V. Danilov
Publikováno v:
Problems of Atomic Science and Technology, Ser. Thermonuclear Fusio. 36:3-25
ОАО «Ордена Ленина Научно-исследовательский и конструкторский институт энерготехники им. Н.А. Доллежаля», Москва, Россия В настоящей ст
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae8e760b5afc31bc5f4732fc56f2ab4f
https://doi.org/10.21517/0202-3822-2013-36-3-3-25
https://doi.org/10.21517/0202-3822-2013-36-3-3-25
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8a5e5b03f2035fe4d805a5d0dae41f65
https://doi.org/10.1016/j.fusengdes.2012.03.038
https://doi.org/10.1016/j.fusengdes.2012.03.038
Autor:
N. Yukhnov, Yu.C. Strebkov, I.V. Danilov, A.Yu. Leshukov, A.A. Dzhanelidze, I.A. Kartashev, S.A. Zhivotov, M.N. Sviridenko, E.V. Tolstikova, V.G. Kovalenko, N.K. Vladimirova, V. Kapyshev, V. Poliksha
Publikováno v:
Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. 34:40-49
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::300e2aef6eb383242e5437258afea14c
https://doi.org/10.21517/0202-3822-2011-34-4-40-49
https://doi.org/10.21517/0202-3822-2011-34-4-40-49
Autor:
A.Yu. Leshukov, V.G. Kovalenko, A.V. Razmerov, V.K. Kapyshev, I.A. Kartashev, Y. Strebkov, M.N. Sviridenko
Publikováno v:
Fusion Engineering and Design. 85:1807-1813
Russian Federation has adopted the strategy to participate in the TBM Program on the rights of “Partner” in the development of ceramic helium-cooled (CHC) test blanket module (TBM) concept. In this connection one of the possible collaboration sce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::288ed528d44b2dee13053c38b7d141c1
https://doi.org/10.1016/j.fusengdes.2010.05.043
https://doi.org/10.1016/j.fusengdes.2010.05.043
Autor:
Yu.C. Strebkov, V. Poliksha, V.G. Kovalenko, I.A. Kartashev, N. Yukhnov, V. Kapyshev, M.N. Sviridenko, A.Yu. Leshukov
Publikováno v:
Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. 33:13-22
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c12685b7102c542be00b405bb414433f
https://doi.org/10.21517/0202-3822-2010-33-3-13-22
https://doi.org/10.21517/0202-3822-2010-33-3-13-22
Autor:
V.A Divavin, I.A Kartashev, A.A Malkov, O.L Schipakin, A.V Lipko, V.M Komarov, A.P Ogorodnikov, M. M. Golovanov, I.V Vitkovsky, I.R Kirillov
Publikováno v:
Fusion Engineering and Design. :703-707
The RF Home Team lithium-cooled test blanket module (TBM) is one of the TBMs to be tested in international thermonuclear experimental reactor (ITER). To satisfy ITER safety demands, the TBM is enclosed in helium-cooled shell. So, it simulates DEMO re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::29fbe1efc3171a46538b4d2a76eb119e
https://doi.org/10.1016/s0920-3796(00)00175-7
https://doi.org/10.1016/s0920-3796(00)00175-7