Radiation-Induced Segregation

Nastar, Maylise; Soisson, Frédéric

doi:10.1016/b978-0-08-056033-5.00035-5

Cited by 62 publications

(80 citation statements)

References 112 publications

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“…The driving force for V elimination in out-of-equilibrium systems [50][51][52][53][54] depends on the excess vacancy concentration with respect to the equilibrium ½V. Even in high-purity Fe, V driving forces will be systematically overestimated because, as we have shown, interstitial solutes increase ½V at thermal equilibrium.…”

Section: Vxmentioning

confidence: 90%

Equilibrium Vacancy Concentration Driven by Undetectable Impurities

et al. 2015

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By means of ab initio calculations combined to statistical mechanics, we provide new evidence that an experimentally undetectable tiny amount of impurities can be responsible for drastic changes in vacancy concentrations ([V]), inducing large deviations from an Arrhenius law even at low temperature. It is the case of O and N in α-Fe. The present finding is fully compatible with existing experiments, and changes the previous common vision that C has the dominant effect. This study provides a route for bridging the longstanding theoretical-experimental gap on the prediction of [V] in metals.

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Section: Vxmentioning

confidence: 90%

Equilibrium Vacancy Concentration Driven by Undetectable Impurities

et al. 2015

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“…In these alloys, it is well established that under irradiation Cr depletes and Ni segregates at GBs [11,12]. However, as pointed out by Marwick et al [13] and Nastar et al [9], it is not clear if this process is driven by the vacancy fluxes (as suggested by the thermal diffusion coefficients: D cr > D Fe > D Ni ) or by the interstitial fluxes (through the formation of interstitialsolute complexes). Furthermore, a sink effect link to GB boundary disorientation was also pointed out by Watanabe et al [14].…”

Section: Introductionmentioning

confidence: 93%

“…RIS/RIP and radiation-induced depletion (RID) mechanisms occur in materials in the presence of point defect (PD) (vacancy or interstitial) fluxes [7][8][9]. The irradiation induces PD fluxes towards the various microstructural sinks: grain boundaries (GBs), free surfaces, radiation damage such as dislocation loops, dislocation lines or even heterophase fluctuations, where the recombination rate is higher than in the matrix [10].…”

Section: Introductionmentioning

confidence: 99%

Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe–Cr alloys

et al. 2014

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“…The radiation-induced segregation phenomenon stems from the off-diagonal terms of the total transport matrix 43 . Equation 2 shows that without V S pairs there would be no flux coupling, and that the sign of the flux coupling depends on the association/dissociation term, the mobility contribution being always positive.…”

Section: B Transport Coefficients Frameworkmentioning

confidence: 99%

Transport properties of C and O in UN fuels

et al. 2017

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Uranium nitride fuel is considered for fast reactors (GEN-IV generation and space reactors) and for light water reactors as a high-density fuel option. Despite this large interest, there is a lack of information about its behavior for in-pile and out-of-pile conditions. From the present literature, it is known that C and O impurities have significant influence on the fuel performance. Here, we perform a systematic study of these impurities in the UN matrix using electronic-structure calculations of solute-defect interactions and microscopic jump frequencies. These quantities were calculated in the DFT+U approximation combined with the occupation matrix control scheme, to avoid convergence to metastable states for the 5f levels. The transport coefficients of the system were evaluated with the self-consistent mean-field theory. It is demonstrated that carbon and oxygen impurities have different diffusion properties in the UN matrix, with O atoms having a higher mobility, and C atoms showing a strong flux coupling anisotropy. The kinetic interplay between solutes and vacancies is expected to be the main cause for surface segregation, as incorporation energies show no strong thermodynamic segregation preference for (001)-surfaces compared with the bulk.

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Radiation-Induced Segregation

Cited by 62 publications

References 112 publications

Equilibrium Vacancy Concentration Driven by Undetectable Impurities

Equilibrium Vacancy Concentration Driven by Undetectable Impurities

Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe–Cr alloys

Transport properties of C and O in UN fuels

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