Self-diffusion in the ? and ? phases of uranium

Bochvar, A. A.; Kuznetsova, Valentina G.; Sergeev, V. S.; Butra, F. P.

doi:10.1007/bf01115328

Cited by 3 publications

(3 citation statements)

References 7 publications

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“…The self-diffusion along the [010] direction is believed to be much more difficult than in the other two directions [19]. The activation energy of self-diffusion in pure uranium along all three principal directions has been obtained experimentally and is reported as 1.91 eV [20] along the [100] and [001] directions, and 2.91 eV [21] along the [010] directions. The corrugated structure does not affect the diffusion parallel to the (010) plane significantly.…”

Section: Introductionmentioning

confidence: 99%

“…The corrugated structure does not affect the diffusion parallel to the (010) plane significantly. As illustrated in [21], the measurement of the diffusion coefficient along the [010] direction is more difficult than for the other two directions. There is only one report in the literature for the [010] direction, and no experiment details are available [21].…”

Section: Introductionmentioning

confidence: 99%

“…As illustrated in [21], the measurement of the diffusion coefficient along the [010] direction is more difficult than for the other two directions. There is only one report in the literature for the [010] direction, and no experiment details are available [21]. For the [100] and [001] directions, there are more reports in the literature, and more experiment details are available [20].…”

Section: Introductionmentioning

confidence: 99%

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First-principles study of diffusion of interstitial and vacancy in α U–Zr

Huang

Wirth

2011

J. Phys.: Condens. Matter

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Metallic uranium-zirconium alloys are of interest for a variety of fast reactor designs, and there is substantial experience with the behavior of metallic fuels. Yet, there remain a number of questions regarding the mechanisms controlling fission-gas-driven swelling in these alloys. Here we present results of ab initio calculations of the diffusion behavior of interstitial and vacancy point defects in α U-Zr alloys. The formation energy and migration barrier of vacancy and interstitial defects, and the influence of Zr on these values, is obtained and compared with experimental results. Our results confirm that self-diffusion in pure α U is via a simple vacancy mechanism, and shows anisotropic character. The calculated values of activation energy are consistent with the experimental results in the literature. For interstitial diffusion, the kick-out mechanism was found to have the smallest energy barrier. The calculations of point defects, and later Xe, in U-Zr alloys will provide a foundation for computational modeling of fission gas bubble nucleation and growth.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%