Search Results - "Evtikhin, V.A"

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  1. 1

    Numerical and experimental determination of metallic solubilities in liquid lithium, lithium-containing nonmetallic impurities, lead and lead-lithium eutectic by Lyublinski, I.E., Evtikhin, V.A., Pankratov, V.Yu, Krasin, V.P.

    Published in Journal of nuclear materials (01-09-1995)
    “…Theoretical correlations based on the empirical model of Miedema et al. have been used to obtain the solubility of transition metals in low-melting metals. A…”
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    Journal Article
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  3. 3

    The tests of liquid metals (Ga, Li) as plasma facing components in T-3M and T-11M tokamaks by Mirnov, S.V., Evtikhin, V.A.

    Published in Fusion engineering and design (01-02-2006)
    “…The experimental study of liquid metals (Ga, Li) as tokamak Plasma Facing Component (PFC) was undertaken in Russian T-3M and T-11M tokamaks ( I p ≤ 100 k A, B…”
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    Journal Article
  4. 4

    Li-CPS limiter in tokamak T-11M by Mirnov, S.V., Lazarev, V.B., Sotnikov, S.M., Evtikhin, V.A., Lyublinski, I.E., Vertkov, A.V.

    Published in Fusion engineering and design (01-04-2003)
    “…This paper is a review of the experimental investigations of Li-behavior as limiter material in real tokamak. All experiments were performed in tokamak T-11M…”
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  5. 5

    Experimental study of lithium MHD flow in slotted channel from V–4Ti–4Cr alloy by Lyublinski, I.E., Evtikhin, V.A., Vertkov, A.V., Ezhov, N.I., Shcherbakov, V.M.

    Published in Fusion engineering and design (01-11-2005)
    “…MHD pressure drop in flowing liquid metal for a tokamak with high magnetic fields is a key concern regarding the development of lithium self-cooled test module…”
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    Journal Article
  6. 6

    Preliminary analysis on a liquid lithium limiter in capillary porous system (CPS) configuration in view of a “litization” experiment on FTU tokamak by Apicella, M.L., Mazzitelli, G., Lazarev, V.B., Azizov, E.A., Mirnov, S.V., Petrov, V.G., Evtikhin, V.A., Lyublinski, I.E., Vertkov, A.V., Lucca, F., Ferdinando, E. Di, Mazzone, G., Ramogida, G., Roccella, M.

    Published in Fusion engineering and design (01-11-2005)
    “…The possibility of using liquid lithium as plasma facing component for the divertor target plates will be investigated on FTU by employing an innovative…”
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    Journal Article Conference Proceeding
  7. 7

    Research of lithium capillary-pore systems for fusion reactor plasma facing components by Evtikhin, V.A., Vertkov, A.V., Lyublinski, I.E., Khripunov, B.I., Petrov, V.B., Mirnov, S.V.

    Published in Journal of nuclear materials (01-12-2002)
    “…To date there is no adequate solution for high heat load plasma facing components of the next step fusion reactor among solid material options. A…”
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    Journal Article
  8. 8

    Technological aspects of lithium capillary-pore systems application in tokamak device by Evtikhin, V.A, Lyublinski, I.E, Vertkov, A.V, Mirnov, S.V, Lazarev, V.B

    Published in Fusion engineering and design (01-10-2001)
    “…The paper concerns two problems. First, the usage of a lithium material basing on capillary-pore systems as a material of rail limiter working in conditions of…”
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    Journal Article
  9. 9

    Some features of beryllium corrosion behavior in Be–liquid Li–V–4Ti–4Cr alloy system by Kupriyanov, I.B., Bazaleev, E.N., Kurbatova, L.A., Lyublinski, I.E., Vertkov, A.V., Evtikhin, V.A.

    Published in Fusion engineering and design (01-11-2005)
    “…Recent experimental results on beryllium corrosion behavior in a V–4Ti–4Cr alloy, liquid lithium static system during testing for 200–500 h at temperatures…”
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  10. 10

    Influence of alloying and impurity element contents on V–Ti–Cr alloy properties by Evtikhin, V.A., Lyublinski, I.E., Vertkov, A.V., Votinov, S.N., Dedyurin, A.I.

    Published in Journal of nuclear materials (01-12-2002)
    “…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%…”
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    Journal Article
  11. 11

    Calculation and experimental investigation of fusion reactor divertor plate and first wall protection by capillary-pore systems with lithium by Evtikhin, V.A., Lyublinski, I.E., Vertkov, A.V., Belan, V.G., Konkashbaev, I.K., Nikandrov, L.B.

    Published in Journal of nuclear materials (01-05-1999)
    “…Estimations and experimental studies on the possibility of capillary-pore systems with lithium as the first wall and divertor target plate plasma-facing…”
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  12. 12

    Energy removal and MHD performance of lithium capillary-pore systems for divertor target application by Evtikhin, V.A, Lyublinski, I.E, Vertkov, A.V, Yezhov, N.I, Khripunov, B.I, Sotnikov, S.M, Mirnov, S.V, Petrov, V.B

    Published in Fusion engineering and design (01-11-2000)
    “…Experimental results of complex studies of lithium capillary-pore systems (CPS) for application as a plasma facing structure in divertor and on the first wall…”
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    Journal Article
  13. 13

    Self-healing electrical insulating coating processes for vanadium alloy–lithium systems by Vertkov, A.V, Evtikhin, V.A, Lyublinski, I.E

    Published in Fusion engineering and design (01-11-2001)
    “…The existing technological approaches for the formation of nitride- and oxide-based self-healing electrical insulating coatings for vanadium alloy–lithium…”
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  14. 14

    Liquid lithium surface research and development by Khripunov, B.I., Petrov, V.B., Shapkin, V.V., Pleshakov, A.S., Rupyshev, A.S., Antonov, N.V., Litnovsky, A.M., Prokhorov, D.Yu, Shpansky, Yu.S., Evtikhin, V.A., Lyublinsky, I.E., Vertkov, A.V.

    Published in Journal of nuclear materials (01-03-2003)
    “…A liquid metal surface made with a capillary porous structure (CPS) (solid base) filled with lithium (liquid) has been offered for application in a magnetic…”
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    Journal Article
  15. 15

    Development of a liquid-metal fusion reactor divertor with a capillary-pore system by Golubchikov, L.G., Evtikhin, V.A., Lyublinski, I.E., Pistunovich, V.I., Potapov, I.N., Chumanov, A.N.

    Published in Journal of nuclear materials (01-10-1996)
    “…The absence of a satisfactorily developed fusion reactor (FR) divertor approach (having no lost layers of sputtered plate materials and/or replaceable blocks)…”
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  16. 16

    Lithium surface operating under steady-state power load by Khripunov, B.I., Petrov, V.B., Shapkin, V.V., Antonov, N.V., Pleshakov, A.S., Rupyshev, A.S., Prokhorov, D.Yu, Evtikhin, V.A., Lyublinsky, I.E., Vertkov, V.V.

    Published in Fusion engineering and design (01-04-2003)
    “…A liquid lithium surface is considered for application in divertor of a fusion tokamak-reactor. Lithium surface has been realized in experimental mock-ups and…”
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    Journal Article Conference Proceeding
  17. 17

    Experimental study of lithium target under high power load by Khripunov, B.I., Petrov, V.B., Shapkin, V.V., Pleshakov, A.S., Rupyshev, A.S., Antonov, N.V., Litnovsky, A.M., Romanov, P.V., Shpansky, Yu.S., Evtikhin, V.A., Lyublinsky, I.E., Vertkov, A.V.

    Published in Journal of nuclear materials (01-03-2001)
    “…This paper presents experimental research on simulation of a free liquid lithium surface under high heat flux impact for divertor application. Capillary porous…”
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  18. 18

    Compatibility of vanadium alloys and its weld joints in homogeneous and heterogeneous liquid lithium systems by Evtikhin, V.A, Lyublinski, I.E, Vertkov, A.V

    Published in Journal of nuclear materials (01-10-1998)
    “…The self-cooled liquid lithium fusion reactor blanket concept has considerable attractions. Liquid lithium compatible structure materials working at high…”
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  19. 19

    Lithium-vanadium experimental facility for blanket problems investigation by Evtikhin, V.A, Lyublinski, I.E, Vertkov, A.V, Korjavin, V.M

    Published in Fusion engineering and design (01-03-1995)
    “…This paper describes a new experimental liquid-lithium facility for investigation of the corrosion-mass transfer and stability of electrical insulator…”
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    Journal Article
  20. 20

    The vanadium alloys technological and corrosion studies in construction and operation of liquid metal facilities for fusion reactor by Vertkov, A.V., Evtikhin, V.A., Lyublinski, I.E.

    Published in Journal of nuclear materials (01-10-1996)
    “…The vanadium—lithium test facility has been constructed to carry out corrosion tests of vanadium alloys in lithium flow, to evaluate the welding procedures and…”
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