Search Results - "Morozov, A.M"

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  1. 1

    Prediction of the effects of thermal ageing on the embrittlement of reactor pressure vessel steels by Margolin, B.Z., Yurchenko, E.V., Morozov, A.M., Chistyakov, D.A.

    Published in Journal of nuclear materials (01-04-2014)
    “…A new method has been proposed for prediction of the effects of thermal ageing on the embrittlement of reactor pressure vessel (RPV) steels. The method is…”
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    Journal Article
  2. 2

    Analysis of a link of embrittlement mechanisms and neutron flux effect as applied to reactor pressure vessel materials of WWER by Margolin, B.Z., Yurchenko, E.V., Morozov, A.M., Pirogova, N.E., Brumovsky, M.

    Published in Journal of nuclear materials (01-03-2013)
    “…The effect of neutron flux on embrittlement of WWER RPV materials is analyzed for cases when different radiation defects prevail. Data bases on the…”
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    Journal Article
  3. 3

    Investigation of the radiation resistance of the alloy SAV-1 irradiated to fluence ~3.5 x [10.sup.22] [cm.sup.-2] by Konoplev, K.A, Fridman, S.R, Orlov, S.P, Ilatovskii, V.A, Morozov, A.M, Petrov, V.A, Petelin, A.L, Izhutov, A.L

    Published in Atomic energy (New York, N.Y.) (01-09-2015)
    “…The results of a study of the radiation resistance of the alloy SAV-1, which is the primary structural material of VVR-M reactor, are presented. During…”
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    Journal Article
  4. 4

    Method for detecting significant patterns in panel data analysis by Kirilyuk, I. L., Kuznetsova, A. V., Sen’ko, O. V., Morozov, A. M.

    “…The paper considers the use of a method for the identification and verification of significant patterns to find clear and measurable differences between groups…”
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  5. 5

    Small-angle neutron scattering investigation of the nanostructure of the SAV-1 alloy irradiated with fast neutrons to high fluences by Lebedev, V. M., Lebedev, V. T., Orlov, S. P., Margolin, B. Z., Morozov, A. M.

    Published in Physics of the solid state (2014)
    “…The supra-atomic structure in samples of the SAV-1 alloy (unirradiated and irradiated with fast neutron fluences of 3.48 × 10 22 n/cm 2 ) has been investigated…”
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    Journal Article
  6. 6

    Analysis of Relationship Between the Radiation Embrittlement Mechanisms and the Influence of Neutron Flux in Respect of WWER Reactor Pressure Vessel Materials by Margolin, B. Z., Yurchenko, E. V., Morozov, A. M., Pirogova, N. E.

    Published in Strength of materials (01-07-2013)
    “…The paper addresses the effect of neutron flux for WWER reactor pressure vessel materials in the cases where various embrittlement mechanisms prevail. The data…”
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