Journal ArticleDOI
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
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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.About:
This article is published in Journal of Nuclear Materials.The article was published on 2005-05-15. It has received 478 citations till now.read more
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Materials Challenges in Nuclear Energy
Steven J. Zinkle,Gary S. Was +1 more
TL;DR: In this article, the three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues.
Journal ArticleDOI
Recent Developments in Irradiation-Resistant Steels
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.
Journal ArticleDOI
Structural materials for fission & fusion energy
Steven J. Zinkle,Jeremy T Busby +1 more
TL;DR: In this article, a strategy for designing high-performance radiation-resistant materials is based on the introduction of a high, uniform density of nanoscale particles that simultaneously provide good high temperature strength and neutron radiation damage resistance.
Journal ArticleDOI
Designing Radiation Resistance in Materials for Fusion Energy
TL;DR: In this article, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination.
Journal ArticleDOI
On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys
TL;DR: In this paper, an extensive experimental study characterizing the sequence of events that lead to the formation of a very high density of Y-Ti-O solute nanoclusters (NC) in mechanically alloyed, hot isostatically pressed ferritic stainless steels is reported.
References
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Journal ArticleDOI
Perspective of ODS alloys application in nuclear environments
Shigeharu Ukai,Masayuki Fujiwara +1 more
TL;DR: In this article, the authors reviewed the JNC activities on ODS steel development as "nano-composite materials" and concluded that the ODS-technology development achieved in the field of fast reactors should be effectively spun off to the fusion reactor first wall and blanket structural materials to allow for safe and economical reactor design.
Journal ArticleDOI
Overview No. 3 Fracture-mechanism maps and their construction for f.c.c. metals and alloys
TL;DR: Fracture-mechanism maps are diagrams with tensile stress as one axis and temperature as the other, showing the fields of dominance of a given micromechanism of fracture: cleavage, ductile fracture, rupture, intergranular creep fracture, and so on as mentioned in this paper.
Journal ArticleDOI
Atom probe tomography of nanoscale particles in ODS ferritic alloys
Michael K Miller,Edward A. Kenik,Kaye F Russell,L. Heatherly,David T. Hoelzer,Philip J. Maziasz +5 more
TL;DR: An atom probe tomography characterization of the microstructure of mechanically-alloyed, oxide-dispersion-strengthened (MA/ODS) ferritic alloys has been performed.
Journal ArticleDOI
Tensile and creep properties of an oxide dispersion-strengthened ferritic steel
Ronald L. Klueh,Philip J. Maziasz,Ick Soo Kim,L. Heatherly,David T. Hoelzer,Naoyuki Hashimoto,Edward A. Kenik,Kazuya Miyahara +7 more
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.
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Perspective of ODS alloys application in nuclear environments
Shigeharu Ukai,Masayuki Fujiwara +1 more