Výsledky vyhledávání - "Yu.I. Kazennov"

Materials and fabrication technology of modules intended for irradiation tests of blanket tritium-breeding zones in Russian fusion reactor projects

Autor: D. Davydov, A. Shikov, N. Shishkov, A Ioltukhovskiy, V. Frolov, Yu.S. Strebkov, Yu.I. Kazennov, V. Tebus, V. A. Gorokhov, V.G. Kovalenko, V. Kapychev, N Shishkin

Publikováno v: Journal of Nuclear Materials. :1429-1433

This paper surveys the modules and materials of blanket tritium-breeding zones developed in the Russian Federation for fusion reactors. Synthesis of lithium orthosilicate, metasilicate and aluminate, fabrication of ceramic pellets and pebbles and exp

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5004709f2a288c37b7e0d6ac448cb2ea
https://doi.org/10.1016/s0022-3115(00)00389-5

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Development of ceramic breeding zone models and mock-up of a DEMO blanket for in-pile irradiation testing

Autor: V. Demidov, A. Lopatkin, D. Davydov, Yu.I. Kazennov, N. Shishkov, V. Kapychev, A. Marachev, V. Shishkin, V.G. Kovalenko, Yu.S. Strebkov, V. Tebus, A. Shikov, V. Frolov

Publikováno v: Plasma Devices and Operations. 8:187-199

A goal of demonstration fusion reactor (DEMO) with ceramic helium cooled (CHC) blanket test module (BTM) is to demonstrate the breeding capability that would lead to tritium self-sufficiency in the ITER reactor and to extract a high-grade heat suitab

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ce5a603589bd6dac6021635842bdb8e3
https://doi.org/10.1080/10519990008228764

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XHM-1 alloy as a promising structural material for water-cooled fusion reactor components

Autor: V. P. Kondrat'ev, V. N. Stepankov, M.I. Solonin, T. A. Krasina, A. B. Alekseev, V.N. Rechitsky, V.F. Khramtsov, Yu.I. Kazennov, S.N. Votinov

Publikováno v: Journal of Nuclear Materials. :586-591

Experience gained in utilizing austenitic stainless steel components in water-cooled power reactors indicates that the main cause of their failure is the steel's propensity for corrosion cracking. In search of a material immune to this type of corros

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7655e7afb80294127347ec599515f54a
https://doi.org/10.1016/s0022-3115(96)00297-8

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Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors

Autor: Yu.S. Strebkov, S.E. Bougaenko, V.B. Ivanov, A.V. Sidorenkov, V.P. Kondratjev, V.M. Chernov, Yu.I. Kazennov, S.N. Votinov, G.A. Birgevoj, V.M. Trojanov, V.A. Kazakov, A.E. Rusanov, I.E. Lyublinski, V.A. Evtikhin, E.O. Adamov, V. Tebus, A. D. Nikulin, M.I. Solonin

Publikováno v: Journal of Nuclear Materials. :370-375

Vanadium-based alloys are most promising as low activation structural materials for DEMO. It was previously established that high priority is to be given to V-alloys of the VTiCr system as structural materials of a tritium breeding blanket and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::86cc15639a7bee9532290fd14b6d0036
https://doi.org/10.1016/s0022-3115(96)00284-x

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In-pile irradiation effected changes in high chromium steel weld joints

Autor: A. V. Minaev, E. A. Krylov, Yu.I. Kazennov, R.Hh. Gibadullin, V. V. Brovko

Publikováno v: Journal of Nuclear Materials. :305-308

Weld joints in 11–14% Cr steels were studied after their exposure in fast reactor at 70–550°C at damaging doses up to 40 dpa. Independent of the phase and chemical compositions weld joints as in-pile irradiated at temperatures below 400°C are s

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::66fe2630c6bbbf8fb1f3ac5c17d19eae
https://doi.org/10.1016/s0022-3115(96)00063-3

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Comparison of mechanical properties and structure of vanadium alloys relevant to DEMO conditions of the first wall and blanket

Autor: A.V. Tselischev, E.G. Mironova, A. B. Alekseev, I.V. Golikov, N.I. Budilkin, V.F. Khramtsov, Yu.I. Kazennov

Publikováno v: Journal of Nuclear Materials. :431-437

Base metal flat specimens and specimens with weld joint of two vanadium alloys V4Ti4Cr and V10Ti5Cr were tested for a tension at 20–700°C. At all temperatures of tests V10Ti5Cr alloy specimens of base metal have higher values of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3b8abfa1f625de10a174b43581b81e39
https://doi.org/10.1016/s0022-3115(96)00283-8

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Vanadium alloys as structural materials for fusion reactor blanket

Autor: M.M. Potapenko, A. D. Nikulin, V. I. Khrustalev, V. M. Tebus, M.I. Solonin, V. P. Kondrat'ev, Yu.I. Kazennov, S.N. Votinov, A. B. Alekseev

Publikováno v: Plasma Devices and Operations. 4:177-185

The results of the investigations of vanadium-base alloys which are considered as perspective material for the first wali and tritium blanket of thermonuclear reactor are given. Data for the influence of alloying on the metallurgical technological ef

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d2d7635c3662e2a6e34ad77345090bc3
https://doi.org/10.1080/10519999608225571

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Feasibility of using high chromium nickel-base alloys in compliance with criteria of iter first wall material serviceability

Autor: V. N. Stepankov, S.N. Votinov, V. P. Kondrat'ev, A. B. Alekseev, Yu.I. Kazennov, V.F. Khramtsov, M.I. Solonin, T. A. Krasina

Publikováno v: Plasma Devices and Operations. 4:267-272

The main requirement, showed to properties materials of the first wall ITER, is their high corrosion-radiating resistance in water at temperature 200-350oC under neutron flux 10-30 dpa. Besides the materials should have high complexes of physical and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::aba70fc54b54ee9109d8f7ecf1c5f334
https://doi.org/10.1080/10519999608225580

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