Diffusion of tritium in zircaloy-2

Greger, G.U.; Münzel, H.; Kunz, Willfried; Schwierczinski, A.

doi:10.1016/0022-3115(80)90381-5

Cited by 27 publications

(13 citation statements)

References 7 publications

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“…Summaries of published results were provided by Greger et al [5] and Watanabe et al [20]. The former authors used a novel tritium implantation method to determine the diffusivity in Zircaloy-2.…”

Section: Diffusivity In Dilute Phase-resultsmentioning

confidence: 99%

“…5.1 shows the temperature dependences of the diffusion coefficients in terms of an Arrhenius plot. In this figure, taken from Greger et al [5], results in the literature that were obtained using hydrogen as the diffusing species have been normalized to that for tritium by multiplying the data by 1/H3 to account for the isotopic mass difference. The justification for the use of this simple relationship in scaling the diffusion coefficients to account for the effect that isotopic mass has on the diffusion rate was based on the experimental results of Gulbransen and Andrew [6].…”

Section: Diffusivity In Dilute Phase-resultsmentioning

confidence: 99%

“…5.16 derived from the phenomenological theory of irreversible thermodynamics (in the linear approximation) where the gradient of the chemical potential is the driving force for diffusion. Equation 5.34 can be converted to one involving the gradient of the activity coefficient instead of the gradient of the chemical potential by using the relation between chemical potential and activity coefficient given by Eq. 5.17 and using the chain rule for partial differentiation as before.…”

Section: Diffusivity-theorymentioning

confidence: 99%

See 2 more Smart Citations

Diffusion of Hydrogen

Püls

2012

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

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Section: Diffusivity In Dilute Phase-resultsmentioning

confidence: 99%

Section: Diffusivity In Dilute Phase-resultsmentioning

confidence: 99%

Section: Diffusivity-theorymentioning

confidence: 99%

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Diffusion of Hydrogen

Püls

2012

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

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“…Nevertheless, the variability of the material parameters concerning the hydrogen diffusion and solubility limit is high from one study to the other. For instance, more than 50% variability in the diffusion coefficient has been reported (comparison of data in [34,35,51,52,53,54,55,56,57,58,59,60]). A calculation considering an increase by 30% of the diffusion coefficient results in a 300 µm blister in 20h (Figure 6(d)).…”

Section: Optimized Thermal Conditions For Blister Formationmentioning

confidence: 99%

Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes

Ménibus

Auzoux

Dieye

et al. 2014

Journal of Nuclear Materials

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This article is focused on the formation of hydride blisters in zirconium alloys an experimental and theoritical standpoint, and their characterization in terms of morphology, hydrides crystallographic phases, hardness and hydrogen concentration. An experimental setup was developed to grow hydride blisters on pre-hydrided Zircaloy-4 cladding tubes by thermo-diffusion. The thermal conditions were optimized based on thermo-diffusion calculations, that take into account the hysteresis in the hydrogen solubility limit, to obtain a high blister growth rate. Micro X-Ray Diffraction (XRD), nano-hardness and Elastic Recoil Detection Analysis (ERDA) showed that the blisters contain a hydrogen gradient, with pure δ-hydride phase close to the external surface over one third of the blister depth. thermo-diffusion * Tel.: +33 1 69 08 39 43; e-mail: arthur.hellouin-de-menibus@cea.fr 1 calculations showed these half thickness blisters should grow in only a few days in PWR conditions. Eventually, the Diffusion Equilibrium Threshold (DET) was defined as a criterion that limits the blister growth, and emphasizes that the hysteresis in the hydrogen solubility limit in zirconium must be taken into account to model hydrogen thermo-diffusion in zirconium alloys.

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“…Greger, et al [140] have reviewed H diffusion in Zr. The diffusivities reported in studies they cite and in others is plotted in Figure 17.…”

Section: < Figure 17 Here>mentioning

confidence: 99%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

121

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Tritium and deuterium induce radiation in reactor materials and some radioactive tritium gas may be released. Most of the materials used in fusion reactors are metals that have relatively high permeabilities for tritium. The fusion community has been working on barriers to minimize tritium release. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments.This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The necessary parameters for tritium release calculations for various regions of a fusion reactor are given.

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Diffusion of tritium in zircaloy-2

Cited by 27 publications

References 7 publications

Diffusion of Hydrogen

Diffusion of Hydrogen

Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes

Tritium Barriers and Tritium Diffusion in Fusion Reactors

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