Search Results - "Négyesi, M."

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    The influence of hydrogen on oxygen distribution inside Zry-4 fuel cladding by Négyesi, M., Burda, J., Bláhová, O., Linhart, S., Vrtílková, V.

    Published in Journal of nuclear materials (30-09-2011)
    “…► Influence of H on O distribution inside Zry-4 fuel cladding was examined. ► O concentration at oxide/metal interface is independent of the H content. ► H…”
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    Journal Article
  3. 3

    Assessment of oxygen diffusion coefficients by studying high-temperature oxidation behaviour of Zr1Nb fuel cladding in the temperature range of 1100–1300°C by Négyesi, M., Chmela, T., Veselský, T., Krejčí, J., Novotný, L., Přibyl, A., Bláhová, O., Burda, J., Siegl, J., Vrtílková, V.

    Published in Journal of nuclear materials (01-01-2015)
    “…The paper deals with high-temperature steam oxidation behaviour of Zr1Nb fuel cladding. First of all, comprehensive experimental program was conducted to…”
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    Journal Article
  4. 4

    Microstructure evolution in Zr1Nb fuel cladding during high-temperature oxidation by Négyesi, M., Bláhová, O., Adámek, J., Siegl, J., Přibyl, A., Vrtílková, V.

    Published in Journal of nuclear materials (30-09-2011)
    “…► Microstructure inside Zr1Nb fuel cladding was observed. ► The α-Zr(O) thickness kinetics is slower compared to Zry-4 alloy. ► The (α + β)-Zr thickness…”
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    Journal Article
  5. 5

    Contribution to the study of the pseudobinary Zr1Nb–Oxygen phase diagram by local oxygen measurements of Zr1Nb fuel cladding after high temperature oxidation by Négyesi, M., Burda, J., Klouček, V., Lorinčík, J., Sopoušek, J., Kabátová, J., Novotný, L., Linhart, S., Chmela, T., Siegl, J., Vrtílková, V.

    Published in Journal of nuclear materials (2012)
    “…► Oxygen concentrations inside oxidized fuel claddings were measured. ► A part of pseudobinary Zr1Nb–O phase diagram has been constructed. ► The phase diagram…”
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    Journal Article
  6. 6

    Proposal of new Oβ oxidation criterion for new types of the Zr1Nb alloy of fuel claddings by Négyesi, M., Klouček, V., Lorinčík, J., Novotný, L., Kabátová, J., Linhart, S., Adámek, J., Siegl, J., Vrtílková, V.

    Published in Nuclear engineering and design (01-08-2013)
    “…► Oxygen concentrations inside oxidized fuel claddings were measured. ► The oxygen concentration threshold of the β-phase embrittlement has been assessed. ►…”
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    Journal Article
  7. 7

    SIMS and thermal evolution analysis of oxygen in Zr-1%Nb alloy after high-temperature transitions by Lorincik, J., Klouc̆ek, V., Negyesi, M., Kabátová, J., Novotný, L., Vrtilkova, V.

    Published in Surface and interface analysis (01-01-2011)
    “…The concentration of oxygen in the primary β‐phase of Zr‐1%Nb alloy was investigated using SIMS and thermal evolution analysis (TEA). The specimens were…”
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    Journal Article Conference Proceeding
  8. 8

    Proposal of new O( beta ) oxidation criterion for new types of the ZrlNb alloy of fuel claddings by Negyesi, M, Kloucek, V, Lorincik, J, Novotny, L, Kabatova, J, Linhart, S, Adamek, J, Siegl, J, Vrtilkova, V

    Published in Nuclear engineering and design (01-08-2013)
    “…This paper deals with oxygen concentration measurements and mechanical testing of nonirradiated modified E110 nuclear fuel cladding tubes exposed to low- and…”
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    Journal Article
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