Search Results - "Mikheev, E.N."

  • Showing 1 - 13 results of 13
Refine Results
  1. 1

    E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures by Fedotov, A. V., Mikheev, E. N., Missorin, D. S., Rysev, N. M.

    Published in Atomic energy (New York, N.Y.) (01-08-2022)
    “…The initial and final melting temperatures of standard, optimized, and modernized zirconium alloy of the E110 type were determined. The stability of zirconium…”
    Get full text
    Journal Article
  2. 2

    Study of the Technical Characteristics of Low-Enriched Uranium Hexafluoride in Long-Time Storage by Yakovlev, D. M., Gromov, O. B., Metelkin, Yu. A., Utrobin, D. V., Mikheev, E. N.

    Published in Atomic energy (New York, N.Y.) (01-10-2021)
    “…Investigations of the physicochemical characteristics of low-enriched uranium hexafluoride stored for up to 12 years in 1 m 3 containers confirmed the…”
    Get full text
    Journal Article
  3. 3

    Sublimation enthalpies of terbium and lutetium triiodides and formation enthalpies of their monomer and dimer molecules by Motalov, V.B., Dunaev, A.M., Mikheev, E.N., Kudin, L.S., Butman, M.F., Krämer, K.W.

    Published in Calphad (01-03-2019)
    “…The sublimation of terbium and lutetium triiodides was studied by Knudsen effusion mass spectrometry. The temperature dependencies of partial vapor pressures…”
    Get full text
    Journal Article
  4. 4

    Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces by Butov, V. G., Solonenko, V. A., Yashchuk, A. A., Lysikov, A. V., Mikheev, E. N., Timchenko, S. N.

    Published in Atomic energy (New York, N.Y.) (2022)
    “…An engineering model for sintering of fuel pellets is presented. The model is based on a previous, fully developed, mathematical model, which was implemented…”
    Get full text
    Journal Article
  5. 5

    Investigation of the Properties of Uranium-Molybdenum Pellet Fuel for VVER by Karpyuk, L. A., Novikov, V. V., Mikheev, E. N., Lysikov, A. V., Sivov, R. B., Fedotov, A. V., Degtyarev, N. A., Missorin, D. S., Bakhteev, O. A.

    Published in Atomic energy (New York, N.Y.) (01-05-2022)
    “…The results of an investigation of the density, microstructure, thermophysical properties, and melting point of uranium-molybdenum pellets produced by powder…”
    Get full text
    Journal Article
  6. 6

    Prospective Accident-Tolerant Uranium-Molybdenum Metal Fuel by Karpyuk, L. A., Lysikov, A. V., Maslov, A. A., Mikheev, E. N., Novikov, V. V., Orlov, V. K., Titov, A. O.

    Published in Atomic energy (New York, N.Y.) (01-07-2021)
    “…Selection criteria based on density and uranium capacity are presented for fuel to be used in accident-tolerant fuel rods. The optimal composition of the…”
    Get full text
    Journal Article
  7. 7
  8. 8

    Evaluation of the Possibility of Fabricating Uranium-Molybdenum Fuel for VVER by Powder Metallurgy Methods by Lysikov, A. V., Mikheev, E. N., Karpyuk, L. A., Sivov, R. B., Bakhteev, O. A., Degtyarev, N. A., Missorin, D. S.

    Published in Atomic energy (New York, N.Y.) (01-03-2020)
    “…It is shown that the technological scheme for fabricating uranium dioxide pellets is suitable for fabricating uranium-molybdenum pellets. It permits using the…”
    Get full text
    Journal Article
  9. 9

    Theoretical and experimental density OF [O.sub.2] by Fedotov, A.V, Mikheev, E.N, Lysikov, A.V, Novikov, V.V

    Published in Atomic energy (New York, N.Y.) (01-04-2013)
    “…An analytical expression is obtained for calculating the theoretical density of a stoichiometric, equilibrium, solid solution of the type…”
    Get full text
    Journal Article
  10. 10

    Fracture Toughness of VVER and PWR Uranium-Dioxide Fuel Pellets with Different Grain Size by Novikov, V. V., Sivov, R. B., Mikheev, E. N., Fedotov, A. V.

    Published in Atomic energy (New York, N.Y.) (01-06-2015)
    “…The results of experimental studies of crack formation and fracture toughness of VVER and PWR uranium dioxide fuel pellets with different grain size are…”
    Get full text
    Journal Article
  11. 11

    Methodology and Results of Investigation of Radiation Creep in Large-Grain Uranium Dioxide Based Fuel by Mikheev, E. N., Fedotov, A. V., Novikov, V. V., Malygin, V. B., Izhutov, A. L., Rogozyanov, A. Ya, Il’inykh, G. A.

    Published in Atomic energy (New York, N.Y.) (01-05-2014)
    “…Three series of investigations of the radiation creep of modified uranium dioxide with grain size ≥25 μm were conducted, using methods and experimental means…”
    Get full text
    Journal Article
  12. 12

    Thermophysical properties of modified oxide nuclear fuel by Baranov, V. G., Pokrovskii, S. A., Tenishev, A. V., Khlunov, A. V., Mikheev, E. N., Fedotov, A. V.

    Published in Atomic energy (New York, N.Y.) (01-05-2011)
    “…In connection with the need for using modified oxide nuclear fuel in VVER, the thermophysical characteristics of alloyed pellets have been measured in the…”
    Get full text
    Journal Article
  13. 13

    Results of expert interrogation of the potential users of gas-analyzers by Kurepko, A.V., Mikheev, E.N., Trukhin, A.V.

    “…Gas-analyzers are intended for the signal system and measurement of concentration of dangerous gases. The users of such devices are the employees in various…”
    Get full text
    Conference Proceeding