Microstructure evolution in Zr1Nb fuel cladding during high-temperature oxidation

Negyesi, Martin; Bláhová, Olga; Adámek, J.; Přibyl, A.; Vrtílková, Věra

doi:10.1016/j.jnucmat.2011.06.015

Cited by 7 publications

(2 citation statements)

References 9 publications

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“…Cladding tubes as a separator between fuel and coolant and a container of fuel in nuclear reactors are exposed to oxidation and/or corrosion, creep and irradiation. The oxidation of zirconium based claddings has extensively been studied by many dierent methods worldwide with the aim to improve the cladding corrosion performance for extended fuel burn ups [1,2]. However, despite the intensive eorts spent in improving the corrosion resistance of claddings, the mechanisms responsible for improved corrosion resistance are not known in detail.…”

Section: Introductionmentioning

confidence: 99%

Creep Behaviour of a Zr-1 wt% Nb Alloy at Elevated Temperatures

et al. 2015

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This paper presents experimental data regarding creep behaviour of a Zr1 wt% Nb alloy at elevated (623 K) and at high temperatures (8731123 K) corresponding to loss-of-cooling situation of fuel cladding tubes for nuclear reactors. For an elaboration of methodological procedure and comparison purposes, the tensile creep tests were conducted using both constant stress and constant load over a wide range of applied stress. The substantial dierences in the acquired creep data between constant stress and constant load creep testing were found especially at high stresses and large creep strain levels.

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Section: Introductionmentioning

confidence: 99%

Creep Behaviour of a Zr-1 wt% Nb Alloy at Elevated Temperatures

et al. 2015

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“…Generally, the microstructure consists of the surface oxide layer, the adjacent α-Zr(O) layer and the innermost β-phase, which is marked as prior β-phase after cooling-down to the room temperature. In case of the Zr1Nb alloy α-phase incursions grow from the α-Zr(O) layer towards the β-phase [1,2]. Additionally, α-Zr(O) grains can precipitate inside the β-phase due to exceeding the oxygen solubility limit [3].…”

Section: Introductionmentioning

confidence: 99%

Influence of Hydrogen Content on Microstructure and Mechanical Properties of Zr1Nb Fuel Cladding after High-Temperature Oxidation

Negyesi

Bláhová

Burda

et al. 2015

KEM

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The aim of this study is to investigate the influence of hydrogen on the microstructure and mechanical properties of Zr1Nb fuel cladding after high-temperature oxidation. As-received or pre-hydrided materials were tested. The influence of different cooling rates was examined as well. The microstructure was observed using of light microscopy. Oxygen distribution was measured using X-ray microanalysis. Local mechanical properties were determined by the microhardness and nanohardness measurements. Ring compression testing (RCT) was employed with the aim to obtain the macroscopic mechanical properties. Fractographic analysis was performed after the RCT. The experimental results confirmed that hydrogen as well as the cooling rate substantially influenced the microstructure and affected both local and macroscopic mechanical properties.

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