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Journal ArticleDOI

Tensile and creep properties of an oxide dispersion-strengthened ferritic steel

TL;DR: The tensile and creep properties of two oxide dispersion-strengthened (ODS) steels with nominal compositions of Fe-12Cr-0.4Ti-O3 (12YWT) and Fe-14Cr-2.5W−0.25Y2O3 were investigated in this article.
About: This article is published in Journal of Nuclear Materials.The article was published on 2002-12-01. It has received 214 citations till now. The article focuses on the topics: Creep & Oxide.
Citations
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TL;DR: In this paper, an emerging class of nanostructured ferritic alloys (NFAs) have been proposed for high-performance structural alloys with outstanding properties that are sustained under long-term service in ultrasevere environments.
Abstract: Advanced fission and future fusion energy will require new high-performance structural alloys with outstanding properties that are sustained under long-term service in ultrasevere environments, including neutron damage producing up to 200 atomic displacements per atom and, for fusion, 2000 appm of He. Following a brief description of irradiation damage and damage resistance, we focus on an emerging class of nanostructured ferritic alloys (NFAs) that show promise for meeting these challenges. NFAs contain an ultrahigh density of Y-Ti-O-enriched dispersion-strengthening nanofeatures (NFs) that, along with fine grains and high dislocation densities, provide remarkably high tensile, creep, and fatigue strength. The NFs are stable under irradiation up to 800°C and trap He in fine-scale bubbles, suppressing void swelling and fast fracture embrittlement at lower temperatures and creep rupture embrittlement at high temperatures. The current state of the development and understanding of NFAs is described, along wi...

1,021 citations

Journal ArticleDOI
TL;DR: In this article, the differences and similarities of different ODS steels are explained in terms of the microstructures of the steels, and observations are explained using the properties of the ODS micro-structures.

478 citations

Journal ArticleDOI
TL;DR: In this paper, the mechanical and thermo-physical properties of refractory metal alloys and mechanically alloyed (MA)-oxide dispersion strengthened (ODS) steels are reviewed and their potential for use in space nuclear reactors is examined.

313 citations

Journal ArticleDOI
TL;DR: This study provides compelling evidence that the nanoclusters have a defective NaCl structure with a high lattice coherency with the bcc steel matrix, which seems to be the most important reasons for the unusual stability of the clusters at high temperatures and in intensive neutron irradiation fields.
Abstract: Oxide-dispersion-strengthened steels are the most promising structural materials for next-generation nuclear energy systems because of their excellent resistance to both irradiation damage and high-temperature creep. Although it has been known for a decade that the extraordinary mechanical properties of oxide-dispersion-strengthened steels originate from highly stabilized oxide nanoclusters with a size smaller than 5 nm, the structure of these nanoclusters has not been clarified and remains as one of the most important scientific issues in nuclear materials research. Here we report the atomic-scale characterization of the oxide nanoclusters using state-of-the-art Cs-corrected transmission electron microscopy. This study provides compelling evidence that the nanoclusters have a defective NaCl structure with a high lattice coherency with the bcc steel matrix. Plenty of point defects as well as strong structural affinity of nanoclusters with the steel matrix seem to be the most important reasons for the unusual stability of the clusters at high temperatures and in intensive neutron irradiation fields.

309 citations

Journal ArticleDOI
TL;DR: In this article, four ferritic alloys based on the composition Fe-14Cr-3W-0.4Ti were developed with a predominant dispersion of either oxide particles or nano-size Y-, Ti-, O-rich clusters, or nanoclusters (NC).

211 citations

References
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Journal ArticleDOI
Abstract: As to an oxide dispersion strengthened (ODs) ferritic steel cladding as the promising candidate for long-life core materials of the fast reactors, previously fabricated claddings had inferior internal creep rupture strength in hoop direction and inferior formability due to less ductility. Those unexpected features of ODs claddings are substantially ascribed to the needle-like grain structure excessively elongated along the forming direction. Controlling the grain morphology by applying the recrystallization method to ODs ferritic steel made possible to improve those inferior features. The ranges of Y2O3 and excessive oxygen contents for possibly cold-rolling and recrystallization were revealed, and the effects of extruded temperature and deformation texture on recrystallization characteristics were evaluated. The recrystallized ODs ferritic steel showed superior internal creep rupture strength and ductility. It was demonstrated from those results that cold-rolling manufacturing of ODs cladding at room tem...

143 citations

Journal ArticleDOI
TL;DR: In this article, a set of ODS steels with varying oxide particle dispersion were irradiated at 650°C, using 3.2 MeV Fe + and 330 keV He + ions simultaneously.

139 citations

Journal ArticleDOI
TL;DR: In this article, an oxide dispersion strengthened (ODS) ferritic steel with high temperature strength has been developed in line with low activation criteria for application in fusion power systems and the composition Fe−13.5Cr−2W−0.25Y2O3 was chosen to provide a minimum chromium content to insure fully delta-ferrite stability.

136 citations

Journal ArticleDOI
TL;DR: In this article, chromium concentrations of 2.25, 5, 9, and 12 pct were used to determine the effect of tungsten and vanadium on the performance of two-dimensional (2.25Cr) steels.
Abstract: Ferritic steels containing Cr, W, and V are being developed for fusion reactor applications. These steels would be alternatives to the Cr−Mo steels that are being considered for structural components. Eight experimental steels were produced. Chromium concentrations of 2.25, 5, 9, and 12 pct were used. Steels with these chromium compositions and with 2 pct W and 0.25 pct V were produced. To determine the effect of tungsten and vanadium, 2.25Cr steels were also produced with 2 pct W and no vanadium, and with 0.25 pct V and zero and 1 pct W. A 9Cr steel containing 2 pct W, 0.25 pct V, and 0.07 pct Ta was also studied. For all alloys, carbon was maintained at 0.1 pct. Tempering behavior of the steels was similar to that of the Cr−Mo steels being considered. Tensile studies indicated that the 2.25Cr−2W−0.25V and 9Cr−2W−0.25V−0.07Ta steels had the highest strengths with properties similar to those of the 9Cr−1MoVNb and 12Cr−1MoVW steels, which are the strongest of the Cr−Mo steels of interest.

46 citations