Stability of non-stoichiometric clusters in the MA957 ODS ferrtic alloy

Sakasegawa, Hideo; Legendre, F.; Boulanger, L.; Brocq, M.; Chaffron, L.; Cozzika, T.; Malaplate, J.; Henry, J.; Carlan, Y. de

doi:10.1016/j.jnucmat.2010.12.056

Cited by 69 publications

(30 citation statements)

References 10 publications

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“…Temperature variation leads the grains partial recrystallized through dislocation and point defect recovery. The discrepancy of oxide distribution in fine grains and coarse grains is attributed to the Ostwald ripening mechanism13. A similar heterogeneous structure in SPSed ODS steel was reported by Boulnat14.…”

Section: Resultssupporting

confidence: 61%

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Wang

et al. 2017

Sci Rep

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The world eagerly needs cleanly-generated electricity in the future. Fusion reactor is one of the most ideal energy resources to defeat the environmental degradation caused by the consumption of traditional fossil energy. To meet the design requirements of fusion reactor, the development of the structural materials which can sustain the elevated temperature, high helium concentration and extreme radiation environments is the biggest challenge for the entire material society. Oxide dispersion strengthened steel is one of the most popular candidate materials for the first wall/blanket applications in fusion reactor. In this paper, we evaluate the radiation tolerance of a 9Cr ODS steel developed in China. Compared with Ferritic/Martensitic steel, this ODS steel demonstrated a significantly higher swelling resistance under ion irradiation at 460 °C to 188 displacements per atom. The role of oxides and grain boundaries on void swelling has been explored. The results indicated that the distribution of higher density and finer size of nano oxides will lead a better swelling resistance for ODS alloy. The original pyrochlore-structured Y2Ti2O7 particles dissolved gradually while fine Y-Ti-O nano clusters reprecipitated in the matrix during irradiation. The enhanced radiation tolerance is attributed to the reduced oxide size and the increased oxide density.

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Section: Resultssupporting

confidence: 61%

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Wang

et al. 2017

Sci Rep

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“…For the smaller clusters in the Cr alloy, there is in the APT data a large range of Y:Ti ratios from 1:2 to 1:0 (pure yttria). As noted by Sakasegawa et al, the apparent composition is dependent on the particle size [52], but unlike their findings our Y:Ti ratio increases for a significant proportion of the smaller clusters analysed rather than decreasing. Differences between the MA957 ODS alloy and the alloys examined here, such as impurity content [53] and the processing route, could explain these difference in the behavior of solute clustering at the atomic scale.…”

Section: Discussioncontrasting

confidence: 79%

Effect of Ti and Cr on dispersion, structure and composition of oxide nano-particles in model ODS alloys

et al. 2015

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a b s t r a c tThree model ODS alloys (Fe-0.3Y 2 O 3 , Fe-0.2Ti-0.3Y 2 O 3 and Fe-14Cr-0.2Ti-0.3Y 2 O 3 ) were prepared by ball milling and then hot extrusion to study the effect of Ti and Cr on the size, distribution, crystal structure and composition of the nano-oxide particles. All alloys were characterized by high resolution transmission electron microscopy (HRTEM), atom probe tomography (APT) and synchrotron-X-ray diffraction (S-XRD) to determine the distribution, structure and composition of the oxide nanoparticles samples. The median particle sizes were 9.6 nm, 7.7 nm and 3.7 nm for the Fe-Y 2 O 3 , Fe-Ti-Y 2 O 3 and Fe-Cr-Ti-Y 2 O 3 alloys, respectively, so the presence of Ti resulted in a significant reduction in oxide particle diameter and the addition of Cr gave a further reduction in size. In the Fe-0.3Y 2 O 3 alloy, the particles are found to be bcc Y 2 O 3 , whereas in the other two alloys (Fe-Ti-0.3Y 2 O 3 and Fe-Cr-Ti-Y 2 O 3 ), the oxide particles were found to be structurally consistent with both orthorhombic Y 2 TiO 5 and fcc Y 2 Ti 2 O 7 . Detailed APT studies showed Cr shells around oxide particles of all sizes in the Fe-Cr-Ti-Y 2 O 3 alloy, that a range of cluster compositions are present and that the particle chemistry varies with cluster size. We show that the addition of Cr has a strong effect on both the size and stoichiometry of the particles.

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“…More significant discrepancy is found in coarsen grains of COS-2, much larger size and low density of nano-oxides are shown. This is could be contributed to Ostwald ripening mechanism of precipitates [35]. Newly formed YeTieO nano-oxides can combine each other to form larger oxide due to high local temperature in SPSed sample, which leads the density decreasing and the average size increasing.…”

Section: Basic Processing and Microstructures Of Cos-1 And Cos-2mentioning

confidence: 98%

Microstructure of HIPed and SPSed 9Cr-ODS steel and its effect on helium bubble formation

Xie

et al. 2016

Journal of Nuclear Materials

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Stability of non-stoichiometric clusters in the MA957 ODS ferrtic alloy

Cited by 69 publications

References 10 publications

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Effect of Ti and Cr on dispersion, structure and composition of oxide nano-particles in model ODS alloys

Microstructure of HIPed and SPSed 9Cr-ODS steel and its effect on helium bubble formation

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