Study of variables that affect hydrogen solubility in α + β Zr-alloys

Parodi, Santiago; Ponzoni, L.M.E.; Heras, M.E. De Las; Mieza, J.I.; Domizzi, G.

doi:10.1016/j.jnucmat.2016.05.027

Cited by 19 publications

(4 citation statements)

References 37 publications

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“…TSS values were determined from the inflexion point and the plateau formed after the transition zone [9] and they are indicated in figures 7 and 8. TSS values obtained increase with the temperature increasing, and are similar to those reported in the literature for the PT sample [10]. On the other hand, TSS values for PT-T sample were lower and that can be related to changes in the microstructure.…”

Section: Resultssupporting

confidence: 88%

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Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments

Stella,

Soria,

Gomez

et al. 2023

J. Phys.: Conf. Ser.

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Zirconium (Zr) alloys are widely used in nuclear power plants as fuel cladding and are susceptible to hydrogen (H) degradation. For long operational service, Zr-based components can suffer a mechanism known as Delayed Hydride Cracking (DHC) associated to an increase of the crack propagation velocity by the re-orientation and precipitation of Zr hydride. In this process, the H mobility has a great influence. In the present work, the isothermal diffusion of H in Zr-2.5%Nb specimens obtained from a CANDU pressure tube were studied at consecutive temperatures of 300°C, 350°C, 375°C and 400°C. H content and mobility were quantified by in-situ neutron imaging experiments performed on ANTARES, the cold neutron imaging facility of FRM II. The time evolution of the H concentration across the specimen allowed the determination of diffusion coefficients, and an assessment of the limitations of existing models commonly used to describe H diffusion.

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Section: Resultssupporting

confidence: 88%

“…ppm while the TSS expected at this temperature is close to that value, in the order of 210 wt. ppm [10]. This assumption was validated to the end of the step at 400°C when all H content in the samples were lower that the theoretical TTS and the difference between the maximum and minimum H concentration was in the order of 25 wt.…”

Section: Resultsmentioning

confidence: 72%

Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments

Stella,

Soria,

Gomez

et al. 2023

J. Phys.: Conf. Ser.

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“…The trend of the effect with increasing Ta content shows a decrease in hydrogen solubility at low content, but then reverses this trend and increases it at higher Ta content. The observed hysteresis between cool-down and heat-up TSS of Zr-1.08Nb agrees with that reported by Parodi et al [35] in Zr-2.5Nb aged for 168 h at 500 °C. There is no noticeable difference in this hysteresis with the addition of Ta, the hysteresis is associated with the mechanical properties of the 𝛼 𝑍𝑟 phase [36] and they are expected to change little due to the small amount of Ta atoms added (see Table 1).…”

Section: Hydrogen Solubilitysupporting

confidence: 91%

Effects of thermo-mechanical process on phase transitions, hydrogen solubility and corrosion of Ta-modified Zr-1Nb alloys

Ferreirós

Polack

Lanzani

et al. 2021

Journal of Nuclear Materials

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“…The results of the hydrogen solubility in alloy samples with the equilibrium annealing at 570 °C are summarized in Table 2. If the initial hydrogen concentration of the zirconium sponge (» 45 ppm) is adding to that incorporated by gaseous charging, the TSSD value of Zr-1.08Nb alloy agrees very well with that reported by Khatamian et al [15] for Zr-1Nb alloy aged at 500 °C for 1000 h. The observed hysteresis between cool-down and heat-up TSS of Zr-1.08Nb agrees with that reported by Parodi et al [16] in Zr-2.5Nb aged for 168 h at 500 °C. The general conclusion can be drawn that tantalum addition to Zr-1Nb alloy has a small influence.…”

Section: Effect Of Ta Addition On Hydrogen Solubility In Zr-1nbsupporting

confidence: 89%

TMS 2022 151st Annual Meeting & Exhibition Supplemental Proceedings

2022

The Minerals, Metals &Amp; Materials Series

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Modified Zr-1Nb alloys with Ta additions is a potential strategy to improve structural alloys for nuclear reactors. The effects of Ta on microstructural stability and resistance to corrosion of Zr-1Nb alloys were systematically investigated and elucidated. The (𝛼 + 𝛽) microstructure in Zr-1.05Nb, Zr-0.85Nb-0.20Ta and Zr-0.85Nb-0.40Ta (wt.%) alloys were obtained with the following two thermo mechanical processes after a water quenching from βZr: a) annealed at 570 °C for 3840 h and b) a combination of intermediate annealing temperatures and cold rolled steps. Quantitative EDS-TEM analysis together with DSC measurements were used to characterise the changes in phase compositions and the fraction of beta-phase precipitates. Hydrogen solubility was measured in alloys with the first annealed condition. The Ta additions increase the monotectic transformation temperature, improves the steam corrosion at 400 °C and 10 MPa up to 14 days, and decreases slightly the hydrogen solubility. The higher thermal microstructural stability compared to Ta-free Zr-1Nb alloys provide potential advantages for increases in operating temperature or acceleration of precipitation kinetics during thermomechanical processing.

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Study of variables that affect hydrogen solubility in α + β Zr-alloys

Cited by 19 publications

References 37 publications

Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments

Hydrogen diffusion in Zr-2.5Nb pressure tubes specimens between 300°C-400°C by in-situ neutron imaging experiments

Effects of thermo-mechanical process on phase transitions, hydrogen solubility and corrosion of Ta-modified Zr-1Nb alloys

TMS 2022 151st Annual Meeting & Exhibition Supplemental Proceedings

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