Development of Oxide Dispersion Strengthened Steels for High Temperature Nuclear Structural Applications

Zhu, Hanliang; Wei, Tao; Harrison, Robert; Edwards, L.; Maruyama, Kouichi

doi:10.1007/978-0-85729-493-7_89

Cited by 4 publications

(2 citation statements)

References 44 publications

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“…Although some limited research has in recent years been conducted on the mechanical properties of Friction Stir Welded ODS steels [9][10][11], including the MA956 steel which is the subject of this study, the data is still highly fragmented. This is partly due to the fact that research into FSW of steels is still in its relative infancy [13,14], and partly to the fact that many ODS steel grades proposed for use in nuclear reactors [15] are currently in limited supply. It is therefore difficult to obtain systematic experimental data on a relatively large range of welding parameters and testing temperatures, so that the process parameter windows can be selected for optimal heat input and flow of the plasticised material during welding.…”

Section: Introductionmentioning

confidence: 99%

Mechanical properties and fracture behaviour of ODS steel friction stir welds at variable temperatures

Dawson

Serrano

Hernandez

et al. 2017

Materials Science and Engineering: A

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We have assessed the microstructure and the temperature-dependent mechanical behaviour of five bead-on-plate friction stir welds of Oxide Dispersion Strengthened (ODS) steel, produced using systematic changes to the tool rotation and traverse speed. Friction stir welding can potentially retain the fine dispersion of nanoparticles, and therefore also the high-temperature strength and radiation damage resistance of these materials. Tensile testing was carried out on the MA956 base material at a range of temperatures, from room temperature up to 750°C. The mechanical properties of the welds were investigated via tensile testing at room temperature and at 500°C, together with micro-hardness testing. The welds exhibited similar strength and ductility to the base material at both testing temperatures 2 as welding caused a partial loss of particle strengthening, alongside an increase in grain boundary strengthening due to a greatly refined grain size in the stir zones. The microhardness data revealed a trend of increasing hardness with increasing tool traverse speed or decreasing rotation speed. This was attributed to the smaller grain size and lower nanoparticle number density in the welds created with these parameters. At 500C, the yield stress and ultimate tensile stress of the base material and the welds decreased, due to a progressive reduction in both the Orowan-type particle strengthening and the grain boundary strengthening.

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Section: Introductionmentioning

confidence: 99%

Mechanical properties and fracture behaviour of ODS steel friction stir welds at variable temperatures

Dawson

Serrano

Hernandez

et al. 2017

Materials Science and Engineering: A

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“…A nanosized dispersion of yttrium oxide in the steel matrix improves the mechanical strength, and the resistance to creep and irradiation induced swelling [4]. Presently, oxide dispersion strengthened reduced activation ferritic steels (ODS RAF steels) are the leading structural materials for nuclear applications under investigation in Europe, Japan and the US [1,[5][6][7]. In order to develop these alloys with the demanded mechanical properties and radiation resistance, the manufacturing route still needs to be optimized.…”

Section: Introductionmentioning

confidence: 99%

Microstructure and mechanical behavior of ODS and non-ODS Fe–14Cr model alloys produced by spark plasma sintering

Auger

Castro

Leguey

et al. 2013

Journal of Nuclear Materials

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Abstract:In this work the spark plasma sintering (SPS) technique has been explored as an alternative consolidation route for producing ultra-fine grained Fe-14Cr model alloys containing a dispersion of oxide nanoparti-cles. Elemental powders of Fe and Cr, and nanosized Y 2 O 3 powder have been mechanically alloyed in a planetary ball mill and rapidly sintered in a spark plasma furnace. Two alloys, with nominal compositions Fe-14%Cr and Fe-14% Cr-0.3%Y 2 O 3 (wt.%), have been fabricated and their microstructure and mechanical properties investigated. The results have been compared with those obtained for other powder metal-lurgy processed alloys of the same composition but consolidated by hot isostatic pressing. The SPS tech-nique under the present conditions has produced Fe-14Cr materials that apparently exhibit different microstructures yielding inferior mechanical properties than the counterpart material consolidated by hot isostatic pressing. Although the presence of a dispersion of Y-rich particles is evident, the oxide dis-persion strengthened (ODS) Fe-14Cr alloy consolidated by SPS exhibits poor tensile properties. The extensive decoration of the powder particle surfaces with Cr-rich precipitates and the residual porosity appear to be responsible for the impaired properties of this ODS alloy consolidated by SPS.

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Gamma-Ray Shielding Effectiveness of Some Alloys for Fusion Reactor Design

Singh

Medhat²,

Badiger

2014

J Fusion Energ

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Development of Oxide Dispersion Strengthened Steels for High Temperature Nuclear Structural Applications

Cited by 4 publications

References 44 publications

Mechanical properties and fracture behaviour of ODS steel friction stir welds at variable temperatures

Mechanical properties and fracture behaviour of ODS steel friction stir welds at variable temperatures

Microstructure and mechanical behavior of ODS and non-ODS Fe–14Cr model alloys produced by spark plasma sintering

Gamma-Ray Shielding Effectiveness of Some Alloys for Fusion Reactor Design

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