Zobrazeno 1 - 10
of 189
pro vyhledávání: '"I. Mazul"'
Autor:
Jochen Linke, I. Mazul, B. Riccardi, A.M. Zhitlukhin, N. S. Klimov, R. Giniyatulin, Gianfranco Federici, T. Hirai, D. V. Kovalenko, G. Janeschitz, Mario Merola, S. Pestchanyi, B. Bazylev, L.N. Khimchenko, V.L. Podkovyrov, I.S. Landman, A. Loarte, Gerald Pintsuk, V. S. Koidan
Publikováno v:
Journal of Nuclear Materials. 415:S59-S64
The paper concerns experimental investigations of plasma facing components erosion under the plasma heat loads expected in ITER divertor during transient events such as the Type I Edge-Localized Modes and the disruptions. The experiments were carried
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::274bfac8c2c22730a3c078d34dc34b89
https://doi.org/10.1016/j.jnucmat.2011.01.013
https://doi.org/10.1016/j.jnucmat.2011.01.013
Autor:
A. Makhankov, N. Holstein, Lorenzo Virgilio Boccaccini, I. Ovchinnikov, A. Gervash, Michael Rieth, B. Zeep, G. Janeschitz, V. Kuznetsov, W. Krauss, R. Kruessmann, T. Ihli, A. Moeslang, Prachai Norajitra, I. Mazul, R. Giniyatulin
Publikováno v:
Journal of Nuclear Materials. :1416-1421
Within the framework of the EU power plant conceptual study (PPCS), a He-cooled divertor concept has been investigated at Forschungszentrum Karlsruhe in cooperation with the Efremov Institute. The design goal is to remove a high heat load of at least
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a51527b65a89eb71f41aedaccd9af9aa
https://doi.org/10.1016/j.jnucmat.2007.04.027
https://doi.org/10.1016/j.jnucmat.2007.04.027
Publikováno v:
Journal of Nuclear Materials. :1300-1304
Several carbon-based materials (carbon fibre composites NB 31, NS 31 and UAM-92, doped graphite RGTi-91), were irradiated at about 90 °C in the damage dose range 0.0021–0.13 dpa. Significant reduction of the thermal conductivity of all materials w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::231bc5f355a0cd4a5046c4d9502f4c6d
https://doi.org/10.1016/s0022-3115(02)00961-3
https://doi.org/10.1016/s0022-3115(02)00961-3
Publikováno v:
Journal of Nuclear Materials. :1524-1532
This paper presents the results of the R&D program on the development of the joining technologies, including non-destructive inspection, for the high heat flux components carried out by the three ITER Participating Teams. Reliability requirements and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5dfb14c8d6b56c61328261431a3b0e85
https://doi.org/10.1016/s0022-3115(02)01070-x
https://doi.org/10.1016/s0022-3115(02)01070-x
Autor:
V. Divavin, Dennis L. Youchison, V.R. Barabash, C. Ibbott, R. Giniatullin, A. Labusov, V.L. Komarov, A. Makhankov, N. Berkhov, I. Mazul, Victor Tanchuk, J.M. McDonald, Sergey Grigoriev
Publikováno v:
Fusion Engineering and Design. :337-342
The glancing angle of incident power on the target of a tokamak divertor results in doubled and highly peaked heat flux onto adjacent downstream tile in the case of lost of tile event (LOTE). As a result downstream tile has higher probability to fail
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ff7ae317812faf1d664cf22377415505
https://doi.org/10.1016/s0920-3796(01)00351-9
https://doi.org/10.1016/s0920-3796(01)00351-9
Publikováno v:
Fusion Engineering and Design. 55:219-229
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b308f9ad641f70b7338413c41b71d61f
https://doi.org/10.1016/s0920-3796(01)00212-5
https://doi.org/10.1016/s0920-3796(01)00212-5
Autor:
Hiroshi Kawamura, Steven J. Zinkle, G. Kalinin, C.H. Wu, V. Barabash, S.A. Fabritsiev, M.A. Ulrickson, I. Mazul
Publikováno v:
Fusion Engineering and Design. 55:231-246
Materials R&D for the vessel and in-vesselcomponents has been performed in support ofITER design, and comprised the structural mate-rials (316L(N), CuCrZr, CuAl25, Inconel 718 andTi-alloys), plasma facing materials (Be, W andCFC) and joints of stainl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5bd3934d593bb7038a221c7b44867cd5
https://doi.org/10.1016/s0920-3796(01)00213-7
https://doi.org/10.1016/s0920-3796(01)00213-7
Autor:
L Plöchl, G. Vieider, A. Cardella, Masato Akiba, B.C. Odegard, R. Tivey, V.R. Barabash, I. Mazul
Publikováno v:
Journal of Nuclear Materials. :1248-1252
An extensive program on the development of the joining technologies between armor (beryllium, tungsten and carbon fibre composites) and copper alloys heat sink materials for ITER plasma facing components (PFCs) has been carried out by ITER home teams
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::817f90a56fe0d829930e076fc7f99855
https://doi.org/10.1016/s0022-3115(00)00120-3
https://doi.org/10.1016/s0022-3115(00)00120-3
Publikováno v:
Fusion Technology. 38:277-282
Proposing beryllium as plasma facing armour this paper presents the recent results obtained in Russia in the frame of such activities. Last year testing of actively cooled mock-ups produced by fast brazing of Be onto Cu-alloy heat sink allows to cons
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d7b09614df4e093e4c6ff070bb5443cd
https://doi.org/10.13182/fst00-a36140
https://doi.org/10.13182/fst00-a36140
Autor:
V. Barabash, Mario Merola, Yamada Masao, Yoshihiro Ohara, K. Ioki, P. Lorenzetto, A. Cardella, Toshihisa Hatano, I. Mazul, Y. Strebkov
Publikováno v:
Fusion Technology. 38:326-333
During the engineering design activities of the ITER project, beryllium has been selected as the armour material for the first wall of the primary, baffle and limiter blanket modules. These components have different requirements according to their fu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8bae756e76e981ede40ae2851b703b31
https://doi.org/10.13182/fst00-a36146
https://doi.org/10.13182/fst00-a36146