Kazakhstani material testing Tokamak KTM. project status

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dc.contributor.authorBatyrbekov, E. G.
dc.contributor.authorSkakov, M. K.
dc.contributor.authorTazhibayeva, I. L.
dc.contributor.authorKolodeshnikov, A. A.
dc.contributor.authorShapovalov, G. V.
dc.contributor.authorZarva, D. B.
dc.date.accessioned2016-11-02T08:24:44Z
dc.date.available2016-11-02T08:24:44Z
dc.date.issued2016-07-18
dc.description.abstractCreation of cost-efficient and safe fusion reactor will require the development of special structural materials for first wall, blanket, reactor components, which will be operated under conditions of the high heat fluxes, superconducting magnets, plasma heating systems and other elements. The existing tokamaks and other fusion facilities do not currently allow for conduction of specialized researches of plasma-facing structural materials. Kazakhstani Material Testing Tokamak (hereinafter - KTM) provides for a unique opportunity to conduct materials research and testing of separate units and components of fusion reactors...ru_RU
dc.identifier.citationBatyrbekov, E. G., Skakov, M. K., Tazhibayeva, I. L., Kolodeshnikov, A. A., Shapovalov, G. V., Zarva, D. B., (2016) Kazakhstani material testing Tokamak KTM. project status. 21st International Symposium on Heavy Ion Inertial Fusion. Book of Abstracts. http://nur.nu.edu.kz/handle/123456789/1765ru_RU
dc.identifier.urihttp://nur.nu.edu.kz/handle/123456789/1765
dc.language.isoenru_RU
dc.publisher21st International Symposium on Heavy Ion Inertial Fusion. Autonomous Organization of Education “Nazarbayev University”ru_RU
dc.rightsAttribution-NonCommercial-ShareAlike 3.0 United States*
dc.rights.urihttp://creativecommons.org/licenses/by-nc-sa/3.0/us/*
dc.subjectTokamak KTMru_RU
dc.subjectproject statusru_RU
dc.subjectresearches of plasma-facing structural materialsru_RU
dc.titleKazakhstani material testing Tokamak KTM. project statusru_RU
dc.typeAbstractru_RU

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