Search Results - "Barsuk, V.A."

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    Tungsten recrystallization and cracking under ITER-relevant heat loads by Budaev, V.P., Martynenko, Yu.V., Karpov, A.V., Belova, N.E., Zhitlukhin, A.M., Klimov, N.S., Podkovyrov, V.L., Barsuk, V.A., Putrik, A.B., Yaroshevskaya, A.D., Giniyatulin, R.N., Safronov, V.M., Khimchenko, L.N.

    Published in Journal of nuclear materials (01-08-2015)
    “…The tungsten surface structure was analyzed after the test in the QSPA-T under heat loads relevant to those expected in the ITER during disruptions. Repeated…”
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    Journal Article
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    The investigation of structure, chemical composition, hydrogen isotope trapping and release processes in deposition layers on graphite sample surfaces exposed to DIII-D divertor plasma in extreme conditions by Buzhinskij, O.I, Barsuk, V.A, Otroshchenko, V.G, Markin, A.V, West, W.P, Whyte, D.G

    Published in Fusion engineering and design (01-11-2002)
    “…Graphite components, employed for the protection of the tokamak first wall, limiters and divertors, can be exposed to extremely high loads both during plasma…”
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    Journal Article Conference Proceeding
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    C protective coating under irradiation by QSPA-T intensive plasma fluxes by Buzhinskij, O.I, Barsuk, V.A, Begrambekov, L.B, Klimov, N.S, Otroshchenko, V.G, Putric, A.B

    Published in Physics of atomic nuclei (01-12-2016)
    “…The effect of the QSPA-T pulsed plasma irradiation on the crystalline boron carbide [B.sub.4]C coating was examined. The duration of the rectangular plasma…”
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    Journal Article
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    Renewable boron carbide coating in plasma shots of tokamak Т11-М by Buzhinskij, O.I., Barsuk, V.A., Otroshchenko, V.G.

    Published in Journal of nuclear materials (01-06-2009)
    “…Experimental results on boronization in plasma shots of the tokamak T-11M are presented. Non-toxic and not explosive metacarborane C 2H 12B 10 was used in the…”
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    Journal Article
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    Stainless steel performance under ITER-relevant mitigated disruption photonic heat loads by Klimov, N.S., Linke, J., Pitts, R.A., Zhitlukhin, A.M., Kovalenko, D.V., Podkovyrov, V.L., Barsuk, V.A., Thomser, C., Pintsuk, G., Bazylev, B.N., Giniyatulin, R.N., Budaev, V.P., Khimchenko, L.N.

    Published in Journal of nuclear materials (01-07-2013)
    “…ITER grade stainless steel (SS) 316L(N)-IG was tested in QSPA-T (photons) and JUDITH (electrons) under heat loads relevant to those expected from photon…”
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    Journal Article
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    Renewed first wall coating in plasma shots at the T-11M tokamak by Buzhinskij, O.I., Barsuk, V.A., Otroshchenko, V.G.

    Published in Fusion engineering and design (01-12-2010)
    “…Experimental results on boronization in situ in the tokamak T-11M plasma shots using non-toxic and not explosive metacarborane C 2H 12B 10 are presented. As a…”
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    Journal Article
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    Erosion products of plasma facing materials formed under ITER-like transient load and deuterium retention in them by Putrik, A. B., Klimov, N. S., Gasparyan, Yu. M., Efimov, V. S., Barsuk, V. A., Podkovyrov, V. L., Zhitlukhin, A. M., Yarochevskaya, A. D., Kovalenko, D. V.

    Published in Physics of atomic nuclei (01-12-2015)
    “…Erosion of the plasma-facing materials in particular evaporation of the materials in a fusion reactor under intense transient events is one of the problems of…”
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    Journal Article
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    Renewable first wall coatings in operating plasma devices by Buzhinskij, O.I., Barsuk, V.A., Logvinenko, V.P., Mescheryakov, A.I., Otroshchenko, V.G.

    Published in Journal of nuclear materials (01-10-2011)
    “…Experimental results on boronization in plasma shots at the T-11M tokamak and stellarator L-2M are presented. Nontoxic and nonexplosive metacarborane C2H12B10…”
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    Journal Article
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    Effect of cyclic extremely high loads on behaviour of the ATJ graphite sample exposed to DIII-D divertor plasma by Buzhinskij, O.I., Barsuk, V.A., Otroshchenko, V.G., West, W.P., Whyte, D.G.

    Published in Fusion engineering and design (01-07-2003)
    “…Graphite elements, destined for the protection of the tokamak first wall, divertors and limiters, can be exposed to extremal loads during plasma disruptions…”
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    Journal Article
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    The investigation of structure, chemical composition, hydrogen isotope trapping and release processes in deposition layers on surfaces exposed to DIII-D divertor plasma by Buzhinskij, O.I, Opimach, I.V, Barsuk, V.A, Arkhipov, I.I, West, W.P, Whyte, D, Wong, C.P.C, Wampler, W.R

    Published in Journal of nuclear materials (01-03-1999)
    “…An ATJ graphite sample, arranged to receive parallel heat flux on a small region of the surface, was exposed to DIII-D divertor plasma using the DiMES…”
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    Journal Article
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    The performance of thick B 4C coatings on graphite divertor tiles in the DIII-D tokamak by Buzhinskij, O.I., Barsuk, V.A., Opimach, I.V., Otrozhenko, V.G., Trazhenkov, A.I., West, W.P., Brooks, N.

    Published in Journal of nuclear materials (1996)
    “…Five TS-1792 graphite tiles were coated with a thick B 4C coating with thickness varying from 85 to 180 μm. Tiles were installed in a lower divertor strike…”
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    Journal Article
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    Performance of boron containing materials under disruption simulations and tokamak divertor plasma testing by Buzhinskij, O.I., Opimach, I.V., Barsuk, V.A., Otrozhenko, V.G., Zhitlukhin, A.M., Trazhenkov, A.I., West, W.P., Trester, P., Valentine, P., Watson, R.D., Youchinson, D.L., Gahl, J.M., Crawford, J.F.

    Published in Journal of nuclear materials (01-04-1995)
    “…The behavior of thick B 4C coatings on different graphites under high power electron beam irradiation, pulsed plasma irradiation and under DIII-D divertor…”
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    Journal Article