On the zirconium–oxygen–hydrogen ternary system

Miyake, Masanobu; Uno, Masayoshi; Yamanaka, Shinşuke

doi:10.1016/s0022-3115(98)00779-x

Cited by 40 publications

(16 citation statements)

References 18 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Hydrogen is produced as water splits to form the O 2-ions required for the corrosion process, however, it has a very low solubility in ZrO 2 compared to α-Zr metal [13]. Therefore, any hydrogen within the oxide layer migrates to either the cladding Zr metal, where it is absorbed into the cladding, or to the water.…”

Section: Introductionmentioning

confidence: 99%

The influence of alloying elements on the corrosion of Zr alloys

et al. 2016

View full text Add to dashboard Cite

Density functional theory (DFT) and autoclave corrosion tests in 360°C water were used to investigate the influence of Sb, Sc, Nb and Sn on the corrosion and hydrogen pick-up (HPU) of Zr-alloys. Sc was shown to have a strongly detrimental effect on alloy corrosion resistance. The Nb-Sb-Zr ternary alloy exhibited significantly improved corrosion resistance over Zr-Nb and ZIRLO, and had little measurable HPU after 195 days. The ratio of Sb Zr /Sb• Zr was shown to transition smoothly with applied space charge, implying Sb can act as a buffer to charge imbalance in the oxide layer.

show abstract

Section: Introductionmentioning

confidence: 99%

The influence of alloying elements on the corrosion of Zr alloys

et al. 2016

View full text Add to dashboard Cite

show abstract

“…It is well known that the hydrogen solubility in zirconium oxide ZrO 2 is very low (10 À5 to 10 À4 mol H per mole oxide) compared to that in the metal [8,12]. Consequently, an intact oxide scale on the Zircaloy surface significantly impedes hydrogen uptake by the metal phase, as was also confirmed by some pre-tests [13].…”

Section: Hydrogen Solubility In the Zircaloy-4-oxygen Systemmentioning

confidence: 73%

“…The hydrogen absorption by zirconium alloys was studied extensively in the past, in particular with regard to the embrittlement of cladding material during longterm operation, which is beyond the scope of this work. Some publications also deal with higher temperatures [4][5][6][7][8], but actually only Moalem and Olander [9] published data for the temperature region above 1270 K which is considered in this paper.…”

Section: Introductionmentioning

confidence: 99%

Hydrogen absorption by zirconium alloys at high temperatures

Steinbrück¹

2004

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…a-ZrO 2 (badellyite) was found in the Zr and in the ZrD 2 powder, in which we estimated Zr:O:D::1:0.1:1.9 from the phase assemblage. No free oxide was found on the Ti, but there is a high degree of solubility of O in the octahedral interstices of the a-andb-phases of these metals and even the (oxy)hydrides [10][11][12]. As H typically is found in the tetrahedral interstices of metals, there is usually not direct competition for sites with O.…”

Section: Precursor Materialsmentioning

confidence: 99%

Omega-phase in Ti-Hf-Zr alloys produced by the hydride-cycle methodSpecial issue on Neutron Scattering in Canada.

et al. 2010

View full text Add to dashboard Cite

Abstract:We report the presence of large proportions of u-phase in Ti-Hf-Zr alloys, prepared using the hydride cycle technique. We show that the u-phase extends across the concentration triangle of Ti-Zr-Hf and report the partitioning of the three metals across the two sites in this structure from neutron and X-ray data. We examine the symmetry of the order parameter governing the b-u phase transition and show that a two-step model for the phase transition involving site ordering followed by displacement is not likely to be correct. We suggest that an interstitial solid solution of oxygen and octahedral vacancies exists, and that the observation of any u-phase diffraction pattern of alloys of these metals at ambient temperature and pressure should be viewed as a potential sign of the presence of oxygen in the octahedral interstitial sites. Résumé : Dans cet article, nous rapportons la présence d'une importante proportion de la phase dite u dans les alliages Ti-Hf-Zr, préparés par une technique de cyclage sous hydrogène (hydride cycle). Nous montrons également que la phase u s'étend à travers le diagramme de concentration triangulaire de Ti-Hf-Zr. De plus, à partir de données de diffractions des neutrons, nous trouvons que les trois métaux se répartissent sur les deux sites distincts dans la structure. Nous examinons la symetrie du paramètre d'ordre qui gouverne la transition de phase b-u et nous montrons qu'un modèle à deux étages pour la transition de phase est improbable. Nous suggérons plutôt la présence d'une solution solide interstitielle d'oxygène et de lacunes octaédriques. De plus, si la phase u est observée dans le diagramme de diffraction d'alliages de ces métaux à température et pression ambiente, on doit la considérer comme un signe possible de la présence d'oxygène sur les sites interstitiels octaédriques.

show abstract

On the zirconium–oxygen–hydrogen ternary system

Cited by 40 publications

References 18 publications

The influence of alloying elements on the corrosion of Zr alloys

The influence of alloying elements on the corrosion of Zr alloys

Hydrogen absorption by zirconium alloys at high temperatures

Omega-phase in Ti-Hf-Zr alloys produced by the hydride-cycle methodSpecial issue on Neutron Scattering in Canada.

Contact Info

Product

Resources

About