Výsledky vyhledávání - "S.N. Votinov"

Influence of alloying and impurity element contents on V–Ti–Cr alloy properties

Autor: I.E. Lyublinski, A.V. Vertkov, A.I. Dedyurin, V.A. Evtikhin, S.N. Votinov

Publikováno v: Journal of Nuclear Materials. :591-595

This work presents the results of a property study and analysis of V–Ti–Cr alloys with a total base component concentration of Ti + Cr in the range of 8–30% with consideration of the influence of impurity and possible transmutation elements. Th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f8b69cd05ad621b845d82889d9daef1f
https://doi.org/10.1016/s0022-3115(02)01015-2

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Internal friction and anelastic properties of vanadium and V–Ti–Cr alloys

Autor: V.M. Chernov, A.E. Rusanov, Oleg A. Plaksin, V. A. Stepanov, B. K. Kardashev, L.P. Zavialski, M.I. Solonin, S.N. Votinov, L.M. Krjukova, L.I. Mamaev

Publikováno v: Journal of Nuclear Materials. 257:263-273

Using an acoustic technique of composite oscillator, the effect of preliminary deformation on the amplitude dependence (amplitude range from 10−6 to 3 × 10−4) of ultrasound damping and the Young's modulus (resonance frequencies) for V and V–(4

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7dd77fef32b3524ee6bf854e6cf0cfac
https://doi.org/10.1016/s0022-3115(98)00457-7

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Cr–Ni alloys for fusion reactors

Autor: S.A. Averin, V.N. Rechitsky, Yu. A. Burenkov, S.N. Votinov, V.M. Chernov, M.I. Solonin, A.V Kozlov, V. P. Kondrat'ev, A. B. Alekseev, B. K. Kardashev

Publikováno v: Journal of Nuclear Materials. :1762-1766

Results of comparative study on the physical and mechanical properties, radiation and corrosion resistance of XHM-1 chromium-enriched alloy (44% Cr, Ni-base, 1–2% Mo, Registered name “Bochvalloy”) and stainless steels (00Cr16Ni15Mo3Nb, 06Cr18Ni

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3a900a4fc16443efee3816e5fbb5313d
https://doi.org/10.1016/s0022-3115(98)00406-1

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Results of R&D for lithium/vanadium breeding blanket design

Autor: A.E. Rusanov, S.N. Votinov, D.L. Smith, I.R. Kirillov, Richard F. Mattas, Yu.S. Strebkov, Claude B. Reed, J.-H Park

Publikováno v: Fusion Engineering and Design. :659-668

The self-cooled lithium/vanadium blanket concept has several attractive features for fusion power systems, including reduced activation, resistance to radiation damage, accommodation of high heat loads and operating to temperatures of 650–700°C. T

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9ab27837c0afeecb51acd30eeb2b78c7
https://doi.org/10.1016/s0920-3796(98)00274-9

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Irradiation creep of VTiCr alloy in BR-10 reactor core instrumented experiments

Autor: A.A. Smirnoff, E.A. Krjuchkov, A.S. Kruglov, M.G. Bulkanov, S.N. Votinov, M.P. Nikulin, V.M. Troyanov, J.M. Pevchykh, A.E. Rusanov

Publikováno v: Journal of Nuclear Materials. :381-384

A thin wall tubular-type speciment of 4%Ti–4%Cr vanadium alloy was tested for creep under irradiation in BR-10 reactor at 713–723 K and at 8.6 × 10 18 n/m 2 s fast neutron flux. A fluence at the end of the experiment have reached 5.8 × 10 25 n/

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3e8c0f027c6dde3c5cad50720e3819e1
https://doi.org/10.1016/s0022-3115(96)00033-5

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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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Investigation of vanadium alloys in CTR plasma disruption-simulation experiments

Autor: V. L. Yakushin, N.V. Kraskovskaya, B. A. Kalin, S.N. Votinov, V.I. Vasiliev

Publikováno v: Journal of Nuclear Materials. :390-394

The experimental results of vanadium-based alloys behavior in CTR plasma disruption-simulation experiments have been presented. The samples have been irradiated by high temperature pulsed deuterium plasma fluxes (HTPPF) in an accelerator type MK-200.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::acf7592cd28bf5a435c45f9997416f42
https://doi.org/10.1016/s0022-3115(96)00018-9

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Metallurgical aspects of possibility of 9–12% chromium steel application as a structural material for first wall and blanket of fusion reactors

Autor: A.G. Ioltukhovsky, T.M. Bulanova, A.V. Povstyanko, M. V. Leont'eva-Smirnova, S.N. Votinov, V.P. Kondrat'ev, V.K. Shamardin

Publikováno v: Journal of Nuclear Materials. :299-304

Steels containing 9–12% Cr are considered to be candidate structural materials for the first wall and blanket of a fusion reactor at the operation temperature up to 650°C. The optimal structure, phase composition and the specific chemical composit

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c061aab7e992a7fe1e38da8d93e71b74
https://doi.org/10.1016/s0022-3115(96)00280-2

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Status of vanadium alloys for fusion reactors

Autor: Hee M. Chung, W. van Witzenburg, K. Fukumoto, D.L. Smith, Hideki Matsui, S.N. Votinov

Publikováno v: Journal of Nuclear Materials. :92-99

Advantages of vanadium alloys for fusion reactor structural applications are: low induced activation, excellent thermal stress factor, high strength at elevated temperatures, and superior ductility at low temperatures. Resistance to irradiation damag

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::83da626778c2815d851c7ffdbad415e5
https://doi.org/10.1016/s0022-3115(96)00331-5

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