Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys
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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.About:
This article is published in Journal of Nuclear Materials.The article was published on 2015-10-01 and is currently open access. It has received 198 citations till now. The article focuses on the topics: Alloy & Chromium.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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Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
TL;DR: 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.
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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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Material Selection for Accident Tolerant Fuel Cladding
TL;DR: In this article, a wide range of alternative cladding materials to Zr-based alloys are investigated for accident tolerance, which can be defined as >100X improvement in oxidation resistance to steam or steam-H2 environments at ≥1473 K (1200 K) for short times.
Journal ArticleDOI
Irradiation hardening of pure tungsten exposed to neutron irradiation
Xunxiang Hu,Takaaki Koyanagi,Makoto Fukuda,N.A.P. Kiran Kumar,Lance Lewis Snead,Brian D. Wirth,Brian D. Wirth,Yutai Katoh +7 more
TL;DR: In this paper, a dispersed barrier hardening model informed by the available microstructure data has been used to predict the hardness of pure tungsten samples irradiated in HFIR at 90-850°C to 0.03-2.2°C.
References
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Book
Transmission Electron Microscopy: A Textbook for Materials Science
TL;DR: In this article, the transmission electron microscope (TEM) is used to detect X-ray spectra and images using a combination of parallel-beam diffraction patterns and CBED patterns.
Book
Fundamentals of Radiation Materials Science : Metals and Alloys
TL;DR: Part I Radiation Damage: The Radiation Damage Event, Displacement of Atoms, Damage Cascade, Point Defect Formation and Diffusion, and Damage Cascade as mentioned in this paper, Part II Physical Effects of Radiation Damage, 6 Radiation-Induced Segregation, 7 Dislocation Microstructure, 8 Irradiation-induced Voids and Bubbles, 9 Phase Stability Under Irradiated, Unique Effects of Ion Irradiations, 11 Simulation of Neutron IRradiation Effects with Ions, and Part III Mechanical Effects of radiation Damage.
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
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
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.