Zobrazeno 1 - 10
of 28
pro vyhledávání: '"Epinatiev, A."'
Autor:
V. I. Matveev, I. D. Epinatiev
Publikováno v:
Kontrol'. Diagnostika. :60-63
Autor:
N. A. Ivanova, A. V. Bloshenko, I. D. Epinatiev, V. S. Grigoriev, A. V. Roshchin, A. E. Goncharova, I. V. Kumpanenko
Publikováno v:
Russian Journal of Physical Chemistry B. 9:132-140
The cleaning of the stainless steel surface from 137Cs and 90Sr ions was studied by the peelable polymer film method. An extracting solution of polyvinylbutyral in dioxane containing various crown ether additions to increase the efficiency of extract
Publikováno v:
Fusion Engineering and Design. :775-780
Measurement and diagnostics system for the fusion experimental reactor ITER blanket is discussed in this paper. Diagnostics are proposed to be carried out in three directions: thermalhydraulic parameter measurement; neutron characteristic measurement
Autor:
R. Tivey, S. Chiocchio, G. Janeschitz, L. Bruno, P. Lorenzetto, R. Parker, G. Vieider, R. Jakeman, R. Raffray, A. Lodato, K. Mohri, A Epinatiev, A. Cardella, L. Giancarli, K. Ioki
Publikováno v:
Fusion Engineering and Design. :377-384
The design of the plasma facing components (PFC) in ITER has evolved with the detailed design of the reactor. The structures exposed to the plasma have different requirements according to their functions. The primary wall, surrounding most of the pla
Autor:
A Epinatiev, S Homyakov
Publikováno v:
Fusion Engineering and Design. 27:198-202
A calculation technique of radiation heat transfer analysis for first wall (FW) facilities was realized in RDIPE (Russia) within the frame of ansys code. The problems which appear in the process of finite element model creation and in the process of
Autor:
A.M. Epinatiev, O. L. Shchipakin, S. Eremin, G. Kalinin, I.V. Danilov, V. Khripunov, A. Sidorov, K. Skladnov, A. Kuzmin, Yu.S. Strebkov, A. Antipenkov, A. Butko, A. Chepovski, V. Poliksha, G.E. Shatalov, E. Shiverski, V. Kolganov
Publikováno v:
Fusion Engineering and Design. 14:427-444
The article contains some features of using Li17-Pb83 eutectic as a breeder for ITER/OTR fusion reactor. Described blanket design options aim to reduce electromagnetic loads or relieve eutectic/channel interaction. Eutectic channel stress analysis co
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Autor:
V.A. Belyakov, A.S. Nikiforov, L.V. Tocheniy, A.M. Epinatiev, A. Antipenkov, G.E. Shatalov, S.S. Yakunin, V. V. Orlov, N.A. Monoszon, Z.V. Ershova, A. Sidorov, P.V. Romanov, Yu.S. Strebkov, D.V. Efremov, A.A. Bochvar
Publikováno v:
Fusion Engineering and Design. 8:91-97
For the development of the Experimental Fusion Reactor (OTR) in the USSR a number of research and development programs have to be carried out first. A description is given of these programs.
Publikováno v:
Fusion Engineering and Design; 1998, Vol. 39 Issue: 1 p775-780, 6p
Autor:
Antipenkov, A., Butko, A., Chepovski, A., Danilov, I., Epinatiev, A., Eremin, S., Kalinin, G., Khripunov, V., Kolganov, V., Kuzmin, A., Poliksha, V., Shchipakin, O., Shatalov, G., Shiverski, E., Sidorov, A., Skladnov, K., Strebkov, Yu.
Publikováno v:
Fusion Engineering and Design; April 1991, Vol. 14 Issue: 3-4 p427-444, 18p