Structure of nanoscale copper precipitates in neutron-irradiated Fe-Cu-C alloys

Minov, Boris; Lambrecht, Marlies A.; Terentyev, D.; Domain, Christophe; Konstantinović, M.J.

doi:10.1103/physrevb.85.024202

Cited by 19 publications

(6 citation statements)

References 34 publications

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“…The peak at 269 K (Snoek) is assigned to the Snoek-relaxation process, [22] according to its activation energy of 0.84 eV and relaxation time constant lnτ 0 ¼ À33 s, [22] see Table 1 and 2. This result is found to be in an excellent agreement with the literature, [5,22] which confirms the validity of the measurements and the methodology for extraction of activation energies. Snoek relaxation process corresponds to thermal jumps of interstitial carbon between octahedral positions in the iron lattice.…”

Section: Effects Of Carbon Contentsupporting

confidence: 89%

“…Carbon easily segregates at dislocations and grain boundaries, as well as it binds to neutron irradiation-induced defects such as vacancy, interstitial clusters, and precipitates. [4][5][6] Moreover, microstructural properties of FM phase, such as the dislocation density and grain size, strongly depend on the ratio between carbon and Cr contents, because their presence influences the result of specific thermal treatment, depending also on the cooling rate, time of permanence at austenitizing and tempering temperature. [2] Therefore, a proper understanding of the carbon distribution and its interplay with Cr is necessary to explain irradiation behavior of FeCr alloys.Recently, mechanical properties of neutron-irradiated FeCr alloys and steels, with varying concentrations of Cr, Ni, Si, P, and C, with either ferritic or FM microstructure, have been investigated.…”

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confidence: 99%

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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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Section: Effects Of Carbon Contentsupporting

confidence: 89%

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confidence: 99%

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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“…It has also been shown that, in addition to small SIA clusters [51], small prismatic loops of self-interstitial nature that may form directly in displacement cascades interact strongly and attractively with solutes, especially with P, Si, Mn, Cu and Ni (in order of strength) [52]. The interaction energy depends on whether the solute interacts with the centre or the edge of the loop; it ranges between 0.2 and 0.5 eV and can be as high as 1 eV in the case of P. In addition, both experiments and atomistic studies have shown that carbon-vacancy complexes (possibly nitrogen-vacancy and oxygen-vacancy complexes as well [53]) form abundantly under irradiation [54,55] and act as very efficient traps for gliding prismatic loops [56], with interaction energies as high as 1.3 eV [57]. The existence of an affinity between solute atoms and loops, as revealed by DFT, has been extended to atomistic studies with interatomic potentials using Metropolis Monte Carlo techniques.…”

Section: Mechanism Driving the Formation Of Nano-sized Solute Rich Cl...mentioning

confidence: 99%

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

et al. 2019

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The formation of nano-sized, coherent, solute-rich clusters (NSRC) is known to be an important factor degrading the macroscopic properties of steels under irradiation. The mechanisms driving their formation are still debated. This work focuses on low-Cu reactor pressure vessel (RPV) steels, where solute species are generally not expected to precipitate. We rationalize the processes taking place at the nanometre scale under irradiation, relying on the latest theoretical and experimental evidence on atomic-level diffusion and transport processes. These are compiled in a new model, based on the object kinetic Monte Carlo (OKMC) technique. We evaluate the relevance of the underlying physical assumptions by applying the model to a large variety of irradiation experiments. Our model predictions are compared with new experimental data obtained with atom probe tomography and small angle neutron scattering, complemented with information from the literature. The results of this study reveal that the role of immobilized selfinterstitial atoms (SIA) loops dominates the nucleation process of NSRC.

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“…as an interstitial or in the form of carbides. Moreover, carbon easily segregates at dislocations and grain boundaries, and shows a great affinity to bind with irradiation-induced defects such as vacancies, solute clusters and precipitates 1,2 . Consequently, the carbon distribution has a strong influence on defect formation and mobility, thus affecting the materials mechanical properties including the swelling of irradiated materials.…”

Section: Introductionmentioning

confidence: 99%

Carbon Distribution in Ferritic-Martensitic Fe-Cr-C Alloys

2018

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Carbon distribution in Fe-Cr-C alloys with a variety of Cr concentrations is studied based on internal friction, optical and transmission-electron microscopy. It is found that the carbon distribution strongly depends on initial microstructure, being ferritic or ferritic/martensitic, which is determined by the thermal treatment, and Cr and carbon concentrations. In the quenched alloys, carbon is observed in the form of small carbon-vacancy complexes, most probably two carbon -single vacancy cluster, 2CV, that dissolve at about 500 K. In tempered alloys, the carbon atoms are observed to be uniformly distributed only in Fe-2.5Cr-C alloy, which is fully ferrite. In the alloys with 5-12% of Cr, with ferritic/martensitic microstructure, carbon-Snoek relaxation peak is not observed due to the carbon precipitation, as well as due to atomic carbon being trapped at dislocations and grain boundaries. In both quenched and tempered alloys, the plastic deformation causes the appearance of the broad relaxation peak close to 300 K which could be assigned to dissolution of single carbon -single vacancy, CV, complexes.

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Structure of nanoscale copper precipitates in neutron-irradiated Fe-Cu-C alloys

Cited by 19 publications

References 34 publications

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

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

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

Carbon Distribution in Ferritic-Martensitic Fe-Cr-C Alloys

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