Zobrazeno 1 - 10
of 58
pro vyhledávání: '"G.E. Shatalov"'
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d490b8b0319c60216cd79202c15311fa
https://doi.org/10.1016/j.fusengdes.2008.07.041
https://doi.org/10.1016/j.fusengdes.2008.07.041
Autor:
V. Kapyshev, M.N. Sviridenko, A. Strizhov, A. Leshukov, V. Poliksha, Yu.S. Strebkov, V.G. Kovalenko, G.E. Shatalov
Publikováno v:
Fusion Engineering and Design. 81:199-203
International thermonuclear experimental reactor (ITER) is anticipated as the only one step to DEMO fusion reactor. One of its main objectives is to demonstrate the availability and integration of technologies essential for a fusion reactor by testin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ece48250287636e7c9f72a71b8ed1d11
https://doi.org/10.1016/j.fusengdes.2005.09.019
https://doi.org/10.1016/j.fusengdes.2005.09.019
Publikováno v:
Fusion Engineering and Design. 81:425-432
Following the DEMO design analysis, two test blanket modules (TBM) were chosen in the RF for the development and testing in ITER: ceramic helium-cooled TBM and lithium self-cooled TBM. In the first one, lithium containing ceramics is used for tritium
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::25fe7c01a574f147001935ca1f286e87
https://doi.org/10.1016/j.fusengdes.2005.05.004
https://doi.org/10.1016/j.fusengdes.2005.05.004
Publikováno v:
Fusion Engineering and Design. :93-99
A possibility to use fusion power reactor (FPR) is considered for burning long-life elements of spent nuclear fuel in parallel with energy production. In this study a principal design of FPR blanket was examined for transmutation of long-life minor a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a11091dc5206bb2d68f77f8957dd4fb7
https://doi.org/10.1016/s0920-3796(02)00210-7
https://doi.org/10.1016/s0920-3796(02)00210-7
Publikováno v:
Fusion Engineering and Design. :333-338
The development of DEMO thermonuclear reactor is a part of Russian national program on the fusion process mastering. The DEMO-S (stationary thermonuclear reactor) should be the logic continuation of the ITER-type projects (pulse thermonuclear reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3f70328d6f811166fdbfa802cc447cd
https://doi.org/10.1016/s0920-3796(02)00215-6
https://doi.org/10.1016/s0920-3796(02)00215-6
Autor:
A.A. Borisov, I.M. Izvolsky, Yu.N. Smirnov, S. V. Sheludjakov, Arkady Serikov, N.N. Vasiliev, G.E. Shatalov, E. P. Velikhov, A.V. Desjatov, V. P. Smirnov
Publikováno v:
Fusion Engineering and Design. :1109-1115
Development of industry and agriculture demands a huge fresh water consumption. Exhaust of water sources together with pollution arises a difficult problem of population, industry, and agriculture water supply. Request for additional water supply in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7be14c84a96b7cc8a83c803321eaa7b9
https://doi.org/10.1016/s0920-3796(01)00585-3
https://doi.org/10.1016/s0920-3796(01)00585-3
Autor:
G.E. Shatalov
Publikováno v:
Fusion Engineering and Design. :39-46
ITER goal was specified as one step between now and the DEMO fusion reactor. One of the major issues is the tritium breeding blankets test relevant to future reactors. The major objectives of blanket modules (TBM) experiments in ITER are reduced in c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::69c795fcc7091270a86387cb1c83d9ce
https://doi.org/10.1016/s0920-3796(01)00234-4
https://doi.org/10.1016/s0920-3796(01)00234-4
Publikováno v:
Fusion Engineering and Design. :289-298
A conceptual study of DEMO-S steady state reactor is being carried out in RF. The main goals of the study are aimed at establishing physics and engineering basis and limitations of the reactor. It was assumed that DEMO is a next step after internatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae24c9f3c32375f92abc667bff905c1e
https://doi.org/10.1016/s0920-3796(00)00262-3
https://doi.org/10.1016/s0920-3796(00)00262-3
Publikováno v:
Fusion Engineering and Design. :591-598
The design of RF DEMO-relevant ceramic helium cooled blanket test module (CHC BTM) for testing in international thermonuclear experimental reactor (ITER) is under consideration. The RF concept of DEMO BTM is based upon the breeder inside tube (BIT)-c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0846192905b1545ca2b0e7aea50f8dc2
https://doi.org/10.1016/s0920-3796(00)00289-1
https://doi.org/10.1016/s0920-3796(00)00289-1
Publikováno v:
Scopus-Elsevier
Three dimensional neutronic analysis was performed to determine effects of radiation streaming through ITER ports with installed shield plugs and different diagnostic equipment. Studied were Neutral Particle Analyser (NPA), Neutron Camera Array and L
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::63f692871f440f3a2eb3f654bb836776
https://doi.org/10.1016/s0920-3796(98)00127-6
https://doi.org/10.1016/s0920-3796(98)00127-6