In situ observation of damage structure in ODS austenitic steel during electron irradiation

Oka, Hiroshi; Watanabe, Masashi; Kinoshita, Hiroshi; Shibayama, Tamaki; Hashimoto, Naoyuki; Ohnuki, S.; Yamashita, Shinichiro; Ohtsuka, Satoshi

doi:10.1016/j.jnucmat.2010.12.156

Cited by 56 publications

(29 citation statements)

References 9 publications

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“…This explains why oversized defects lead to many small voids rather than few large ones. These observations also suggest that if any oversized solutes used in the production of ODS steels, such as Y, Hf, and Ti, remain dissolved in the Fe matrix they would contribute to the observed radiation-damage resistance by providing recombination sites in addition to those at the oxide nanoparticle surfaces [7,8].…”

Section: Vacancy Clustering and Void Nucleationmentioning

confidence: 87%

“…Such a low value means that a newly dissociated vacancy is much more likely to return to the solute than be lost to the general matrix (making an ω 0 jump) and it is reasonable to ask why this does not significantly suppress diffusion through the factor F (ω 4 /ω 0 ) in Eq. (8). However, even in the limit where the vacancy always returns, that is, ω 4 /ω 0 → +∞, F remains above zero at 2/7.…”

Section: Vacancy-mediated Solute Diffusionmentioning

confidence: 95%

“…The incorporation of small oxide nanoparticles, such as Y 2 O 3 , is another important technique to strengthen and improve the radiation-damage resistance of both ferritic [5][6][7] and austenitic [8][9][10][11][12] steels, allowing them to be used at higher temperatures and radiation dose rates than standard steels. Small quantities of oversized solutes, such as Ti and Hf, are commonly used in the formation of these oxide dispersion strengthened (ODS) steels to control the size of the oxide nanoparticles.…”

Section: Introductionmentioning

confidence: 99%

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Transition metal solute interactions with point defects in fcc iron from first principles

2015

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We present a comprehensive set of first-principles electronic structure calculations of the properties of substitutional transition metal solutes and point defects in austenite (face-centered cubic, paramagnetic Fe). Clear trends were observed in these quantities across the transition metal series, with solute-defect interactions strongly related to atomic size, and only weakly related to more subtle details of magnetic or electronic structure. Oversized solutes act as strong traps for both vacancy and self-interstitial defects and as nucleation sites for the development of protovoids and small self-interstitial loops. The consequent reduction in defect mobility and net defect concentrations in the matrix explains the observation of reduced swelling and radiation-induced segregation. Our analysis of vacancy-mediated solute diffusion demonstrates that below about 400 K Ni and Co will be dragged by vacancies and their concentrations should be enhanced at defect sinks. Cr and Cu show opposite behavior and are depleted at defect sinks. The stable configuration of some oversized solutes is neither interstitial nor substitutional; rather they occupy two adjacent lattice sites. The diffusion of these solutes proceeds by a novel mechanism, which has important implications for the nucleation and growth of complex oxide nanoparticles contained in oxide dispersion strengthened steels. Interstitial-mediated solute diffusion is negligible for all except the magnetic solutes (Cr, Mn, Co, and Ni). Our results are consistent across several antiferromagnetic states and surprising qualitative similarities with ferromagnetic (body-centered cubic) Fe were observed; this implies that our conclusions will be valid for paramagnetic iron.

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Section: Vacancy Clustering and Void Nucleationmentioning

confidence: 87%

Section: Vacancy-mediated Solute Diffusionmentioning

confidence: 95%

Section: Introductionmentioning

confidence: 99%

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Transition metal solute interactions with point defects in fcc iron from first principles

2015

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“…The helium implantation increases the rate of void swelling and it tends to form coarse precipitates. Helium atoms act as nucleation sites of cavities 18 . Zhang 12 , et al have also reported the instability of phases due to irradiation.…”

Section: Void Swellingmentioning

confidence: 99%

“…In ODS316, the cavities evolve at matrix and cluster interface. The interface between oxide and matrix act as sink for cavities in ODS316 alloy 18 .…”

Section: Void Swellingmentioning

confidence: 99%

Austenitic Oxide Dispersion Strengthened Steels : A Review

2016

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Materials play an important role in the fast breeder reactors. Materials used in cladding tube and fuel pins should have better creep and void swelling resistance. To overcome these difficulties, a new class of material known as oxide dispersion strengthened (ODS) steels are used. There are two groups of ODS steels, the ferritic and the austenitic ODS steels based on the matrix. The present paper reviews the current status of research in austenitic ODS steels. The interaction of dislocations with finely dispersed incoherent, hard particles that governs the strength and high temperature properties of ODS materials is briefly reviewed. The synthesis route adopted for these ODS steels, which is mostly through powder metallurgy route is also discussed. The role of various oxides such as Y2O3, ZrO2and TiO2and the clusters formed in these ODS steels on the mechanical properties and void swelling characteristics is also discussed.

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Effect of In Situ Nano-Particles on the Microstructure and Mechanical Properties of Ferritic Steel

Niu

Tang

Wang

et al. 2016

steel research int.

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Transmission electron microscopy (TEM), optic microscopy (OM), and small-angle-X-ray-scattering(SAXS)are combined to comprehensively characterize the effect of endogenous nano-particles obtained by a new method, on microstructure and mechanical properties of the ferritic steel. Morphology of nano-particles, the change of microstructure, and the performance of steel are systematically studied. Results indicate that the endogenous nano-particles are titanium oxide which not only has a positive effect on refining the structure of ferrite steel, but also can significantly improve its strength without much losing its plasticity. Tensile tests reveal that tensile strength and yield strength of the investigated steel are increased from the original 392 and 247 MPa to 524 and 430 MPa, respectively. However, the value of the elongation-to-failure is only decreased by 3%, reached to 25% ultimately.

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In situ observation of damage structure in ODS austenitic steel during electron irradiation

Cited by 56 publications

References 9 publications

Transition metal solute interactions with point defects in fcc iron from first principles

Transition metal solute interactions with point defects in fcc iron from first principles

Austenitic Oxide Dispersion Strengthened Steels : A Review

Effect of In Situ Nano-Particles on the Microstructure and Mechanical Properties of Ferritic Steel

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