On the role of Ni, Si and P on the nanostructural evolution of FeCr alloys under irradiation

Gómez-Ferrer, B.; Heintze, C.; Pareige, C.

doi:10.1016/j.jnucmat.2019.01.040

Cited by 18 publications

(29 citation statements)

References 44 publications

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“…This is confirmed by several observations of toroidal-shaped and planar solute clusters in RPV steels [17,12,18,19], and has been recently rationalized in an advanced model able to reproduce the microstructure evolution of various RPV steel types [20]. The "pinning" effect on clusters of self-interstitial atoms (SIA) has been inferred experimentally for Mn, P, and Ni [12,7,16,8], and by modeling for Cr, P, and Ni [21,22,23]. Recent ab initio calculations of solute-loop interactions suggest a similar pinning tendency for Mn, Cu, and Si [24].…”

Section: Introductionsupporting

confidence: 70%

“…Our results suggest that these complexes are likely to be vacancy-Ni pairs. In Cr-rich ferritic alloys, segregation of Cr-Si-Ni-P clusters takes place [7,8], due to P atoms diffusing to dislocations and catalyzing the formation and growth of clusters around them. Fig.…”

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

“…Fig. 11 reports a more quantitative evaluation of solute segregation in the following alloys: the Ringhals high-Ni, low-Cu RPV steel [100] and three FeCr alloys, including Wharry's T91 [46] and the two model alloys where P-catalyzed precipitation took place [7,8]. The solute nominal concentrations are reported next to each data point.…”

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

“…Eq. 14) marking solute enrichment in several multicomponent alloys, namely an RPV steel (Ringhals) [100], and three FeCr alloys: T91 (Wharry) [46], Fe-9%Cr (Pareige) [7], and Fe-15%Cr (Gomez-Ferrer) [8]. Each data point reports also the nominal concentration (in at.%) of the corresponding element.…”

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

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Solute diffusion by self-interstitial defects and radiation-induced segregation in ferritic Fe–X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys

et al. 2020

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This work investigates solute transport due to self-interstitial defects and radiation induced segregation tendencies in dilute ferritic alloys, by computing the transport coefficients of each system based on ab initio calculations of binding energies and migration rates. The implementation of the self-consistent mean field method in the KineCluE code allows to extend the calculation of transport coefficients to arbitrary interaction ranges, crystal structures, and diffusion mechanisms. The results show that the diffusivity of P, Mn, and Cr solute atoms is dominated by the dumbbell mechanism, that of Cu by vacancies, while the two mechanisms might be in competition for Ni and Si, despite the fact that the corresponding mixed dumbbells are not stable. Systematic enrichment at defect sinks is expected for P and Mn solutes due to dumbbell diffusion, and for Si due mainly to vacancy drag. Vacancy drag is also responsible for Cu and Ni enrichment below 1085 K. The RIS behavior of Cr is the outcome of a fine balance between dumbbell enrichment and vacancy depletion. Therefore, for dilute Cr concentrations global enrichment occurs below 540 K, and depletion above. This threshold temperature grows with solute concentration. The findings are in agreement with experimental observations of RIS and clustering phenomena, and confirm that solutedefect kinetic coupling plays an important role in the formation of solute clusters in reactor pressure vessel steels and other alloys.However, the capability of PDs (vacancies and self-interstitials) to carry solute atoms to the nucleation sites, although often inferred in simple terms from the solute-PD binding energies, is yet not fully characterized. Nowadays, precise analytical models based on the Self-Consistent Mean Field (SCMF) theory [25] or the Green-function approach [26], in combination with ab initio calculations of defect jump rates, allow for a highly accurate analysis of the intrinsic atomic-transport properties by calculation of the transport (Onsager) matrix [27]. By the latter methods, it has been proven that solute drag by vacancies is a widespread phenomenon arising below a given temperature threshold in body-centered cubic (bcc) [28,29], face-centered cubic (fcc) [30,31,32], and hexagonal close-packed (hcp) metals [33], provided that the vacancy-solute interaction is sufficiently strong.In dilute ferritic alloys, the threshold temperature has been systematically determined for all transition-metal impurities [34,29]. This threshold is near or above 1000 K for Cu, Mn, Ni, P, and Si, whereas it lies near 300 K for Cr. Therefore, vacancies are indeed capable of transporting all solutes to sinks (including nucleation sites), with the exception of Cr for which depletion at sinks is expected.On the other hand, the transport efficiency of self-interstitial atoms (SIA) has been only superficially investigated. Speculations based on ab initio evaluations of the stability of mixed dumbbells (MD) [35,36,37], and the interpretation of resistivity-recovery (RR) experiments [38,...

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Section: Introductionsupporting

confidence: 70%

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 99%

See 2 more Smart Citations

Solute diffusion by self-interstitial defects and radiation-induced segregation in ferritic Fe–X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys

et al. 2020

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“…It is these clusters that are thought to act as nucleation sites for Ni, Si and Cr. Gómez-Ferrer et al [30] further investigated Mn-Ni-Si clusters in model Fe-9Cr alloys to determine whether they are formed by irradiation or thermodynamics. APT was used to investigate the chemical segregation of Fe-9Cr model alloys irradiated with 5 MeV Fe 2+ to 0.1 and 0.5 dpa at 300 o C. These model alloys had a controlled set of alloying additions (P, Ni and Si).…”

Section: Introductionmentioning

confidence: 99%

Nanocluster evolution and mechanical properties of ion irradiated T91 ferritic-martensitic steel

Davis

Auger

Hofer

et al. 2021

Journal of Nuclear Materials

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Magnetic After‐Effect Study of Carbon Distribution and Grain Boundary Diffusion in FeCrC Alloys and Steels

Konstantinović

Prester

Drobac

et al. 2022

Physica Status Solidi (a)

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Herein, carbon distribution and grain‐boundary diffusion processes are studied in a variety of FeCr alloys and steels with different chromium content and microstructure, based on magnetic after‐effect measurements performed in a broad temperature range, from 100 to 1000 K. The existence of three metastable carbon positions in the lattice is revealed in the FeC alloys. Carbon as interstitial in the lattice, segregated at the dislocations and grain boundaries, is represented by the relaxation peaks at about 269, 432, and 607 K, respectively. The relaxation process due to the grain‐boundary self‐diffusion is clearly distinguished from those mentioned earlier, and is observed to be at about 643 and 681 K in low and high carbon Fe, respectively. Addition of Cr has a twofold effect: a) for Cr concentrations higher than about 3 wt% carbon‐related relaxation processes completely disappear from the spectra, most probably due to formation of carbides, b) the solute grain‐boundary diffusion relaxation peak appears in the spectra at about 800 K, with an activation energy that is directly dependent on the Cr content. Activation energy of the solute grain‐boundary diffusion is found to be generally smaller in ferrite–martensite microstructure in comparison with fully ferrite alloys.

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On the role of Ni, Si and P on the nanostructural evolution of FeCr alloys under irradiation

Abstract: h i g h l i g h t s P is the fastest diffuser regarding the formation of the solute-rich clusters. P segregation in clusters saturates between 0.1 and 0.5 dpa. No synergistic effects between Ni, Si and P are observed up to 0.1dpa.

Cited by 18 publications

References 44 publications

Solute diffusion by self-interstitial defects and radiation-induced segregation in ferritic Fe–X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys

Solute diffusion by self-interstitial defects and radiation-induced segregation in ferritic Fe–X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys

Nanocluster evolution and mechanical properties of ion irradiated T91 ferritic-martensitic steel

Magnetic After‐Effect Study of Carbon Distribution and Grain Boundary Diffusion in FeCrC Alloys and Steels

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