Segregation of alloying elements to free surfaces during irradiation

Okamoto, P.R.; Wiedersich, H.

doi:10.1016/0022-3115(74)90267-0

Cited by 318 publications

(58 citation statements)

References 7 publications

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“…Specifically, it was demonstrated in [11][12][13][14] that neutron irradiation a factor responsible for the formation of the α-phase in austenitic steels, such as 304, 316, and Kh18N10T. The generation of this phase under irradiation is associated with the loss of stability of austenite (γ-phase) due to the depletion of the matrix in austenite-producing elements, mainly, nickel.…”

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confidence: 98%

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Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

et al. 2009

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For the assessment of the effect of irradiation-induced swelling on mechanical properties of an irradiated austenitic steel, investigations have been performed on 08Kh18N10T steel -base metal and weld -exposed to damaging dozes close in magnitude, within two different temperature ranges: (a) 330-340°C, where there occurs almost no swelling, and (b) 400-450°Ñ, where a significant level of swelling (3-13%) is observed. Based on the investigation results, the temperature dependence of short-term mechanical properties is plotted for the irradiated metal. A comparative study of magnetization of the metal irradiated at various temperatures has been carried out. Fractographic examination of the tested specimens has been performed.

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confidence: 98%

“…However, the question is what possible alterations in the material can trigger the change in the fracture mechanism. Based on the investigations [11][12][13][14], it can be concluded that irradiation may initiate such structural alterations whereby a change in the fracture mechanism can occur.…”

mentioning

confidence: 99%

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

et al. 2009

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“…These interfaces are of interest since they are potential traps for point defects. They are therefore likely to limit long range diffusion, and with it, degradation of the material from swelling, irradiation creep, or radiation-induced segregation and precipitation [2,[8][9][10][11][12][13][14]. Implementation of this approach requires the ability to control and tune the regime where compositional patterns are stable under irradiation.…”

Section: Introductionmentioning

confidence: 99%

Role of point-defect sinks on irradiation-induced compositional patterning in model binary alloys

2015

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Abstract:The dynamical competition between the chemical mixing forced during energetic particle irradiation and thermally activated decomposition can lead to the stabilization of selforganized steady states in alloy systems comprised of immiscible elements. Continuum modeling and atomistic simulations predicted the stabilization of steady-state nanoscale compositional patterns for a well-defined range of ballistic mixing frequencies normalized by the irradiation-enhanced thermal atomic jump frequencies. Irradiationinduced compositional patterning has now indeed been observed experimentally, but a quantitative comparison has been lacking because models and simulations have relied on a simplified treatment with a fixed point defect concentration. We overcome here this limitation by using a kinetic Monte Carlo (KMC) code that includes the production, recombination, and elimination of point defects at sinks, as well as the chemical mixing forced by ballistic replacements. By varying the sink density and their efficiency, the temperature range of stabilization of steady-state compositional patterns is investigated in model binary alloys for point defect regimes dominated by either recombination or elimination on sinks. We find that in the sink regime, compositional patterning can be extended to remarkably high temperatures. The results are discussed by analyzing the relative diffusivities of A and B species, and their dependencies on temperature.

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“…Dislocation loops and half-loops were also observed in this case, with the growth of loops attributed to interstitial-type loops and the shrinkage to vacancy loops as interstitial defects have larger strain fields compared to vacancies. 28,29) …”

Section: Irradiationmentioning

confidence: 99%

Microstructural Evolution of an Ion Irradiated Ni–Mo–Cr–Fe Alloy at Elevated Temperatures

et al. 2014

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The irradiation behavior of a NiMoCrFe alloy, of the type currently being considered for use in future molten salt cooled reactors, has been investigated in situ using 1 MeV Kr ions at temperatures of 723 and 973 K. When irradiated to 5 dpa, experimental observations reveal the instantaneous formation and annihilation of point defect clusters, with such processes attributed to the long range elastic interactions that occur between defects through multiple intra-cascade overlap. Corresponding differences in the defect cluster density and size distribution suggest that changes to the microstructure were dependent upon temperature and dose, affecting the growth, accumulation and mobility of irradiationinduced defect clusters under these conditions.

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Segregation of alloying elements to free surfaces during irradiation

Cited by 318 publications

References 7 publications

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

Role of point-defect sinks on irradiation-induced compositional patterning in model binary alloys

Microstructural Evolution of an Ion Irradiated Ni–Mo–Cr–Fe Alloy at Elevated Temperatures

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Segregation of alloying elements to free surfaces during irradiation

Cited by 318 publications

References 7 publications

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 1. Relation between irradiation swelling and irradiation embrittlement. Experimental results

Role of point-defect sinks on irradiation-induced compositional patterning in model binary alloys

Microstructural Evolution of an Ion Irradiated Ni&ndash;Mo&ndash;Cr&ndash;Fe Alloy at Elevated Temperatures

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Microstructural Evolution of an Ion Irradiated Ni–Mo–Cr–Fe Alloy at Elevated Temperatures