Evaluation of threshold stress of the MA957 ODS ferrtic alloy

Sakasegawa, Hideo; Chaffron, L.; Legendre, F.; Brocq, M.; Boulanger, L.; Poissonnet, S.; Carlan, Y. de; Béchade, Jean-Luc; Cozzika, T.; Malaplate, J.

doi:10.1016/j.jnucmat.2008.12.151

Cited by 29 publications

(11 citation statements)

References 28 publications

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“…is consistent with a range of 0.15-0.63 reported for other ODS alloys[8,9,28,[36][37][38][39][40][41][42]. He, et al[9] reported a Y:Ti ratio of 0.33 for the same heat of Fe-9%Cr ODS alloy in the present study.…”

supporting

confidence: 92%

The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C

Swenson

Wharry

2015

Journal of Nuclear Materials

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A model Fe-9%Cr oxide dispersion strengthened (ODS) steel was irradiated with protons or neutrons to a dose of 3 displacements per atom (dpa) at a temperature of 500°C, enabling a direct comparison of ion to neutron irradiation effects at otherwise fixed irradiation conditions. The irradiated microstructures were characterized using transmission electron microscopy and atom probe tomography including cluster analysis. Both proton and neutron irradiations produced a comparable void and dislocation loop microstructure. However, the irradiation response of the Ti-Y-O oxide nanoclusters varied. Oxides remained stable under proton irradiation, but exhibited dissolution and an increase in Y:Ti composition ratio under neutron irradiation. Both proton and neutron irradiation also induced varying extents of Si, Ni, and Mn clustering at existing oxide nanoclusters. Protons are able to reproduce the void and loop microstructure of neutron irradiation carried out to the same dose and temperature. However, since nanocluster evolution is controlled by both diffusion and ballistic impacts, protons are rendered unable to reproduce the nanocluster evolution of neutron irradiation at the same dose and temperature.

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supporting

confidence: 92%

The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C

Swenson

Wharry

2015

Journal of Nuclear Materials

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“…High temperature softening may be due the thermal activation of plasticity mechanisms. Especially, Orowan dislocation bypass 16,17 can be significantly enhanced compared to what is expected at room temperature, therefore decreasing the precipitation hardening. These results are encouraging enough to consider investigating the creep behaviour in the next future.…”

Section: Scale-up and Mechanical Propertiesmentioning

confidence: 91%

Assessment of consolidation of oxide dispersion strengthened ferritic steels by spark plasma sintering: from laboratory scale to industrial products

et al. 2014

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Oxide dispersion strengthened steels are new generation alloys that are usually processed by hot isostatic pressing (HIP). In this study, spark plasma sintering (SPS) was studied as an alternative consolidation technique. The influence of the processing parameters on the microstructure was quantified. The homogeneity of the SPSed materials was characterised by electron microprobe and microhardness. A combination of limited grain growth and minimised porosity can be achieved on semi-industrial compact. Excellent tensile properties were obtained compared to the literature. This paper is part of a special issue on Euromat 2013: Emerging technologies in powder metallurgy Highlights N An oxide dispersion strengthened ferritic steel was consolidated by spark plasma sintering. N Scale-up from 15 g to 1/2 kg compacts was achieved with reproducible microstructure and resulting properties. N The chemical homogeneity of the compacts was characterised by electron microprobe analysis and microhardness. N Carbon coming from the graphite foils at the interfaces between the graphite die, the punches and the powder diffused within few hundreds microns into the ferritic matrix. N Precipitation of large titanium oxides ranging from 50 to 200 nm was detected in the compacts.N These coarse particles were not detrimental to the mechanical properties, since both tensile strength and ductility were achieved.

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“…In addition it is consistent with the intermediate creep domain identified by Artz [32] were the Norton exponent is very high. Such high values suggest the existence of a threshold stress [33] below which no creep occurs. Wilshire and Lieu [31] reported a constant value of this stress exponent between 873 K and 973 K which is consistent with the present results obtained at 923 K and 973 K. Fig.…”

Section: Tensionmentioning

confidence: 99%

Mechanical behaviour of ferritic ODS steels – Temperature dependancy and anisotropy

Fournier

Steckmeyer

Rouffié

et al. 2012

Journal of Nuclear Materials

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Evaluation of threshold stress of the MA957 ODS ferrtic alloy

Cited by 29 publications

References 28 publications

The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C

The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C

Assessment of consolidation of oxide dispersion strengthened ferritic steels by spark plasma sintering: from laboratory scale to industrial products

Mechanical behaviour of ferritic ODS steels – Temperature dependancy and anisotropy

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