Investigation of oxide particles in unirradiated ODS Eurofer by tomographic atom probe

Aleev, A. A.; Iskandarov, N. A.; Klimenkov, M.; Lindau, R.; Möslang, A.; Никитин, А. А.; Рогожкин, С. В.; Vladimirov, P.; Залужный, А. Г.

doi:10.1016/j.jnucmat.2010.09.008

Cited by 44 publications

(20 citation statements)

References 14 publications

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“…ODS Eurofer steel contains numerous nanosized Y 2 O 3 particles (partly coherent with the matrix), which are formed directly after hot isostatic pressing of this material [3][4]. APT study of the initial state of this material has revealed a large number (~2 × 10 24 m -3 ) of ultrafine nanosized (1-4 nm) clusters enriched in Y, O as well as V, N [5]. These dispersed oxide inclusions provide extremely high temperature resistance to ODS steels.…”

Section: Introductionmentioning

confidence: 99%

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

et al. 2016

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Advanced reduced activation ferritic/martensitic steels and oxide dispersion-strengthened steels exhibit significant radiation embrittlement under low temperature neutron irradiation. In this study we focused on atom probe tomography (APT) of Eurofer97 and ODS Eurofer steels irradiated with neutrons and heavy ions at low temperatures. Previous TEM studies revealed dislocation loops in the neutron-irradiated f\m steels. At the same time, our APT showed early stages of solid solution decomposition. High density (10 24 m -3 ) of ~3-5 nm clusters enriched in chromium, manganese, and silicon atoms were found in Eurofer 97 irradiated in BOR-60 reactor to 32 dpa at 332°C. In this steel irradiated with Fe ions up to the dose of 24 dpa, pair correlation functions calculated using APT data showed the presence of Cr-enriched pre-phases.APT study of ODS Eurofer found a significant change in the nanocluster composition after neutron irradiation to 32 dpa at 330 °C and an increase in cluster number density. APT of ODS steels irradiated with Fe ions at low temperatures revealed similar changes in nanoclusters.These results suggest that irradiation-induced nucleation and evolution of very small precipitates may be the origin of low temperature radiation embrittlement of f\m steels.

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Section: Introductionmentioning

confidence: 99%

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

et al. 2016

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“…On the other hand, some research on ODS manufacturing shows that yttria does not ''dissolve'' during ball milling, rather the effect is a reduction in size to a few nanometres due to fracturing or amorphization of the yttria which takes place at the interfaces of the matrix (Ref 18,30). In many ODS analyses, the size of the oxide clusters was found to be around 1-4 nm after dissolution and precipitation (Ref [31][32][33][34][35]. Even after heat treatment and coarsening of the particles, oxide clusters of size around 10 nm are observed (Ref 35).…”

Section: Discussionmentioning

confidence: 99%

Incorporation of Y2O3 Particles into 410L Stainless Steel by a Powder Metallurgy Route

Zeybek

Barroso

Chong

et al. 2014

J. of Materi Eng and Perform

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Addition of yttria to steels has been proposed for the fabrication of oxide-dispersion-strengthened materials for nuclear power applications. We have investigated materials prepared from 12 Cr martensitic stainless steel, AISI 410L, produced by powder metallurgy. Materials were produced with and without yttria addition, and two different sizes of yttria were used, 0.9 lm and 50 nm. Tensile and mini-creep tests were performed to determine mechanical properties. Optical microscopy, SEM, TEM, and EDX analysis were used to investigate the microstructures and deformation mechanisms and to obtain information about nonmetallic inclusion particles. SiO 2 , MnS, and Y 2 Si 2 O 7 inclusion particles were observed. An SiO 2 and Y 2 O 3 interaction was seen to have occurred during the ball milling, which impaired the final mechanical properties. Small-angle neutron scattering experiments showed that the matrix chemistry prevented effective dissolution of the yttria.

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“…A first generation of ODS alloys was developed and has been produced in cooperation with Plansee AG (Austria). The microstructure and mechanical properties of these alloys has already been studied [3,[5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20].…”

Section: Introductionmentioning

confidence: 99%

Corrosion behavior of Eurofer 97 and ODS-Eurofer alloys compared to traditional stainless steels

et al. 2011

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In the present work, the corrosion resistance of ferritic-martensitic EUROFER 97 and ODS-EUROFER steels was tested in solutions containing NaCl or H 2 SO 4 and KSCN, both at 25°C. The results were compared to those of AISI 430 ferritic and AISI 410 martensitic conventional stainless steels. The as-received samples were tested by electrochemical techniques, specifically, electrochemical impedance spectroscopy, potentiodynamic polarization curves, and double-loop electrochemical potentiokinetic reactivation tests. The surfaces were observed by scanning electron microscopy after exposure to corrosive media. The results showed that EUROFER 97 and ODS-EUROFER alloys present similar corrosion resistance but lower than ferritic AISI 430 and martensitic 410 stainless steels.

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Investigation of oxide particles in unirradiated ODS Eurofer by tomographic atom probe

Cited by 44 publications

References 14 publications

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

Incorporation of Y2O3 Particles into 410L Stainless Steel by a Powder Metallurgy Route

Corrosion behavior of Eurofer 97 and ODS-Eurofer alloys compared to traditional stainless steels

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