Search Results - "Négyesi, M."
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The influence of hydrogen on oxygen distribution inside Zry-4 fuel cladding
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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Assessment of oxygen diffusion coefficients by studying high-temperature oxidation behaviour of Zr1Nb fuel cladding in the temperature range of 1100–1300°C
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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Microstructure evolution in Zr1Nb fuel cladding during high-temperature oxidation
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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Contribution to the study of the pseudobinary Zr1Nb–Oxygen phase diagram by local oxygen measurements of Zr1Nb fuel cladding after high temperature oxidation
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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Proposal of new Oβ oxidation criterion for new types of the Zr1Nb alloy of fuel claddings
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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SIMS and thermal evolution analysis of oxygen in Zr-1%Nb alloy after high-temperature transitions
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 -
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Proposal of new O( beta ) oxidation criterion for new types of the ZrlNb alloy of fuel claddings
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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