Zobrazeno 1 - 10
of 95
pro vyhledávání: '"V. Chuyanov"'
Publikováno v:
Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. 44:107-110
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::199f6f074c46167d91aa650abc8717c4
https://doi.org/10.21517/0202-3822-2021-44-2-107-110
https://doi.org/10.21517/0202-3822-2021-44-2-107-110
Autor:
I. Berezin, Igor Berishev, N. Moshegov, Alexey Komissarov, V. Chuyanov, P. Trubenko, O. Raisky, Valentin Gapontsev, D. Miftakhutdinov, A. Ovtchinnikov
Publikováno v:
High-Power Diode Laser Technology XV.
We report on high efficiency multimode pumps that enable ultra-high efficiency high power ECO Fiber Lasers. We discuss chip and packaged pump design and performance. Peak out-of-fiber power efficiency of ECO Fiber Laser pumps was reported to be as hi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2faa19bd074d20aae4e84660f658c4d1
https://doi.org/10.1117/12.2250634
https://doi.org/10.1117/12.2250634
Autor:
David Campbell, P.C. Wong, E. Rajendra Kumar, Mu-Young Ahn, Mohamed A. Abdou, Italo Ricapito, Yves Poitevin, C. Pan, M. Zmitko, L. Giancarli, Y. Strebkov, Sadaaki Suzuki, Mikio Enoeda, V. Chuyanov
Publikováno v:
Fusion Engineering and Design. 87:395-402
The objective of the ITER TBM Program is to provide the first experimental data on the performance of the breeding blankets in the integrated fusion nuclear environment. Such information is essential to design and predict the performance of DEMO and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::520d967fad180b8eca8293870e829bd9
https://doi.org/10.1016/j.fusengdes.2011.11.005
https://doi.org/10.1016/j.fusengdes.2011.11.005
Publikováno v:
Fusion Engineering and Design. 85:2005-2011
Tritium breeding blanket testing is an important element in the ITER mission. Up to six different concepts for tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. Successful T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7fa1d450ea465242c8efdd421355c6a2
https://doi.org/10.1016/j.fusengdes.2010.07.005
https://doi.org/10.1016/j.fusengdes.2010.07.005
Autor:
Joseph Snipes, K.P. Chang, A. Tesini, Mario Merola, C. Hansalia, R. Pascal, F.T. Maluta, V. Chuyanov, J.P. Friconneau, C. Gliss, S. Gicquel, O. Bede, M. Benchikhoune, M. Iseli, Laurent Patisson, I. Kuehn, G. Rigoni, G. Dell’Orco, B. Levesy, S. Beloglazov, L. Giancarli, C.S. Kim, I. Yonekawa
Publikováno v:
Fusion Engineering and Design. 85:1829-1833
Up to six mock-ups of different tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. The paper describes the recent studies performed by the IO for the preparation of the most
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d70b0609904e9f2d8333b0a96b541a24
https://doi.org/10.1016/j.fusengdes.2010.06.005
https://doi.org/10.1016/j.fusengdes.2010.06.005
Autor:
Nina Alexandrovna Maximenkova, V. P. Kukhtin, A.V. Belov, I.Yu. Rodin, E. A. Lamzin, V. A. Belyakov, V. M. Amoskov, M. S. Larionov, Sergey Egorov, S. E. Sytchevsky, A.A. Lancetov, Yu. Gribov, A. A. Firsov, V. Ivkin, V. Chuyanov
Publikováno v:
Fusion Engineering and Design. 85:718-723
A feasibility has been demonstrated for numerical reconstruction on the base of magnetic measurements for geometrical displacements or deformations occurred in the manufacture and assembly of magnet coils. For validation of the proposed approach the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cd8e1b9105c91d9495a007beda87df4f
https://doi.org/10.1016/j.fusengdes.2010.04.027
https://doi.org/10.1016/j.fusengdes.2010.04.027
Autor:
David Campbell, A.S. Kukushkin, Masayoshi Sugihara, V. Chuyanov, R.A. Pitts, V. Mukhovatov, A. Loarte, Michiya Shimada
Publikováno v:
Journal of Nuclear Materials. :282-285
This paper describes an important part of ITER Research Plan, on plasma–wall interaction (PWI). In order to maximize the flexibility of the machine during the initial operation (H and D phases), CFC will be used for the targets. Tungsten will be us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::16fc6e21194f5e2a49b14a2d3524898b
https://doi.org/10.1016/j.jnucmat.2009.01.113
https://doi.org/10.1016/j.jnucmat.2009.01.113
Autor:
V. Rozov, L. Wang, T.J. Tanaka, V.R. Barabash, M.A. Ulrickson, V. Chuyanov, P. Lorenzetto, H. Nishi, K. Ioki, Y.H. Jeong, Jiale Chen, I.V. Mazul, X. Wang, A. Gervash, B.G. Hong, F. Elio, Mikio Enoeda, A.T. Peacock
Publikováno v:
Fusion Engineering and Design. 82:1774-1780
To guarantee acceptable quality of 1800 FW panels produced by six different parties (CN, EU, JA, KO, RF and US), a qualification program is essential. The qualification mock-up is 80 mm wide, 240 mm long and 81 mm thick with three beryllium tiles 10
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48c23d9c152142d8a99d81079d8f3c9e
https://doi.org/10.1016/j.fusengdes.2007.02.013
https://doi.org/10.1016/j.fusengdes.2007.02.013
Autor:
S. Cho, E. Kuzmin, K. Ioki, C. Bachmann, Yu. Utin, L. Jones, M. Nakahira, A. Alekseev, G. Sannazzaro, M. Morimoto, V. Chuyanov
Publikováno v:
Fusion Engineering and Design. 82:2040-2046
Recent progress of the ITER vacuum vessel (VV) design is presented. As the ITER construction phase approaches, the VV design has been improved and developed in more detail with the focus on better performance, improved manufacture and reduced cost. B
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4674a2d439827926a2f478eb794d0979
https://doi.org/10.1016/j.fusengdes.2007.07.009
https://doi.org/10.1016/j.fusengdes.2007.07.009
Autor:
Mohamed A. Abdou, Masato Akiba, B.G. Hong, V. Chuyanov, C. Pan, R. Lässer, L. Giancarli, Y. Strebkov
Publikováno v:
Journal of Nuclear Materials. :1271-1280
Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H–H operation. This paper gives an overview of the proposed TBMs designs,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71dcd4329445ff9858b714117e26f995
https://doi.org/10.1016/j.jnucmat.2007.03.234
https://doi.org/10.1016/j.jnucmat.2007.03.234