Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
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In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.About:
This article is published in Journal of Nuclear Materials.The article was published on 2015-10-19 and is currently open access. It has received 320 citations till now. The article focuses on the topics: Zirconium alloy & Zirconium.read more
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Accident tolerant fuel cladding development: Promise, status, and challenges
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
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Current status of materials development of nuclear fuel cladding tubes for light water reactors
Zhengang Duan,Huilong Yang,Yuhki Satoh,Kenta Murakami,Sho Kano,Zishou Zhao,Jingjie Shen,Hiroaki Abe +7 more
TL;DR: In this paper, the impact of alloying elements on the material properties of Zirconium-based claddings has been systematically presented, including the impact on coating layer on the surface of Zr-based alloys, mainly referring coating materials and fabrication methods.
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Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys
TL;DR: In this paper, a series of Fe-Cr-Al alloys with 10 −18 ¼ % Cr and 2.9 −4.9 % Al were irradiated at 382 −C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition.
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Uniform corrosion of FeCrAl alloys in LWR coolant environments
Kurt A. Terrani,Bruce A. Pint,Young-Jin Kim,Kinga A. Unocic,Ying Yang,Chinthaka M. Silva,Harry M. Meyer,Raul B. Rebak +7 more
TL;DR: In this article, the corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors.
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Irradiation-enhanced α′ precipitation in model FeCrAl alloys
Philip D. Edmondson,Samuel A. Briggs,Samuel A. Briggs,Yukinori Yamamoto,Richard H. Howard,Kumar Sridharan,Kurt A. Terrani,Kevin G. Field +7 more
TL;DR: In this paper, the compositional influence on the formation of irradiation-induced Cr-rich α′ precipitates using atom probe tomography was investigated and the average cluster Cr content ranged between 51.1 and 62.5% dependent on initial compositions.
References
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Journal ArticleDOI
Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect
TL;DR: In this article, a model was developed to explain the effects associated with the addition of reactive elements that is based on the segregation of reactive-element ions to scale grain boundaries and the metal-oxide interface.
Journal ArticleDOI
Ferritic/martensitic steels for next-generation reactors
Ronald L. Klueh,Andrew T. Nelson +1 more
TL;DR: In this article, the authors investigated the use of elevated-temperature ferritic/martensitic steels for in-core and out-of-core applications for the next generation of nuclear power reactors.
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Accident tolerant fuels for LWRs: A perspective
Steven J. Zinkle,Steven J. Zinkle,Kurt A. Terrani,Jess C. Gehin,Larry J. Ott,Lance Lewis Snead +5 more
TL;DR: In this article, three general strategies for accident tolerant fuels are explored: modification of current state-of-the-art zirconium alloy cladding to further improve oxidation resistance (including use of coatings), replacement of Zr Alloy cladding with an alternative oxidation resistant high-performance cladding, and replacement of the monolithic ceramic oxide fuel with alternative fuel forms.
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The influence of alloying elements on the development and maintenance of protective scales
TL;DR: In this article, the important principles that determine the establishment, growth and long-term maintenance of protective Cr2O3, Al 2O3 and SiO2 scales on hightemperature iron-, nickel-and cobalt-base alloys are reviewed and discussed.
Journal ArticleDOI
Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors
TL;DR: In the 1970s, high chromium (9-12%Cr) ferritic/martensitic steels became candidates for elevated temperature applications in the core of fast reactors.