Post-irradiation annealing of Ni–Mn–Si-enriched clusters in a neutron-irradiated RPV steel weld using Atom Probe Tomography

Styman, Paul; Hyde, J.M.; Parfitt, David; Wilford, Kieth; Burke, M. G.; English, C.A.; Efsing, Pål

doi:10.1016/j.jnucmat.2015.01.027

Cited by 71 publications

(35 citation statements)

References 19 publications

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“…It is also worth noticing that, for both materials, the number density of TEM‐invisible SIA clusters coincides with that of Mn‐Ni‐rich solute clusters observed by APT , which strongly supports the idea of SIA loops acting as nucleation sites for solute clusters in RPV steels.…”

Section: Resultssupporting

confidence: 78%

“…, where it is also compared with the results of the experimental characterizations. For the Fe–C–MnNi alloy, TEM , APT , and PAS analyses are available, whereas the results for the Ringhals steels can be only compared with the APT characterizations and with the preliminary outcome of a recent PAS study . TEM analyses of irradiated Ringhals samples have excluded the formation of visible (above ≈ 1 nm) defect clusters (i.e., interstitial loops or voids), but did not provide any other quantitative usable indication.…”

Section: Resultsmentioning

confidence: 99%

“…OKMC evolution with dose of the population of self‐interstitial (top panels) and vacancy clusters (bottom panels), for the Fe–C–MnNi model alloy and the Ringhals RPV steel, compared with the experimental characterizations . The population of TEM‐visible clusters ( n SIA > 90 and n V > 45) includes all clusters with a diameter larger than 1 nm.…”

Section: Resultsmentioning

confidence: 99%

“…With the present work, we investigate this possible mechanism, starting from an already validated OKMC model for low‐alloy Fe–C–MnNi steels under neutron irradiation , and extending it to the Ringhals RPV steels. The prediction of the nanostructure evolution in terms of defect‐cluster density and size versus neutron dose is eventually compared to the characterization of the Ringhals RPV surveillance samples, performed with atom probe tomography (APT) and transmission electron microscopy (TEM) analyses.…”

Section: Introductionmentioning

confidence: 99%

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An object kinetic Monte Carlo model for the microstructure evolution of neutron‐irradiated reactor pressure vessel steels

Messina

Chiapetto

Olsson

et al. 2016

Physica Status Solidi (a)

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Phone: þ32 (0)14 33 31 81This work presents a full object kinetic Monte Carlo framework for the simulation of the microstructure evolution of reactor pressure vessel (RPV) steels. The model pursues a "gray-alloy" approach, where the effect of solute atoms is seen exclusively as a reduction of the mobility of defect clusters. The same set of parameters yields a satisfactory evolution for two different types of alloys, in very different irradiation conditions: an Fe-C-MnNi model alloy (high flux) and a high-Mn, high-Ni RPV steel (low flux). A satisfactory match with the experimental characterizations is obtained only if assuming a substantial immobilization of vacancy clusters due to solute atoms, which is here verified by means of independent atomistic kinetic Monte Carlo simulations. The microstructure evolution of the two alloys is strongly affected by the dose rate; a predominance of single defects and small defect clusters is observed at low dose rates, whereas larger defect clusters appear at high dose rates. In both cases, the predicted density of interstitial loops matches the experimental solute-cluster density, suggesting that the MnNi-rich nanofeatures might form as a consequence of solute enrichment on immobilized small interstitial loops, which are invisible to the electron microscope.

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Section: Resultssupporting

confidence: 78%

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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An object kinetic Monte Carlo model for the microstructure evolution of neutron‐irradiated reactor pressure vessel steels

Messina

Chiapetto

Olsson

et al. 2016

Physica Status Solidi (a)

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“…Our results confirm that all solutes but Cr can be indeed dragged to sinks, i.e., solute clustering in RPV steels can occur by kinetic coupling with point defects. A further support to a kinetics-driven phenomenon comes from post-irradiation annealing experiments [15] showing the dissolution of these clusters above 450°C.…”

Section: Comparison With Experimental Ris Observationsmentioning

confidence: 86%

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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Improvement in irradiation resistance of FeCu alloy by pre-deformation through introduction of dense point defect sinks

et al. 2020

Rare Met.

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Post-irradiation annealing of Ni–Mn–Si-enriched clusters in a neutron-irradiated RPV steel weld using Atom Probe Tomography

Cited by 71 publications

References 19 publications

An object kinetic Monte Carlo model for the microstructure evolution of neutron‐irradiated reactor pressure vessel steels

An object kinetic Monte Carlo model for the microstructure evolution of neutron‐irradiated reactor pressure vessel steels

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

Improvement in irradiation resistance of FeCu alloy by pre-deformation through introduction of dense point defect sinks

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