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uranium alloys
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Book: Machining
Series: ASM Handbook
Volume: 16
Publisher: ASM International
Published: 01 January 1989
DOI: 10.31399/asm.hb.v16.a0002192
EISBN: 978-1-62708-188-7
... Abstract This article focuses on the basic metallurgy and machining parameters of classes of depleted and enriched uranium alloys. It provides information on the health precautions applicable to the machining of depleted uranium alloys. The article also discusses tool wear and the types...
Abstract
This article focuses on the basic metallurgy and machining parameters of classes of depleted and enriched uranium alloys. It provides information on the health precautions applicable to the machining of depleted uranium alloys. The article also discusses tool wear and the types of tools used in uranium alloy machining.
Series: ASM Handbook
Volume: 2
Publisher: ASM International
Published: 01 January 1990
DOI: 10.31399/asm.hb.v02.a0001085
EISBN: 978-1-62708-162-7
... Abstract Uranium is a moderately strong and ductile metal that can be cast, formed, and welded by a variety of standard methods. This article presents an overview of the processing and properties of uranium and uranium alloys with a brief overview of the principal hazards and precautions...
Abstract
Uranium is a moderately strong and ductile metal that can be cast, formed, and welded by a variety of standard methods. This article presents an overview of the processing and properties of uranium and uranium alloys with a brief overview of the principal hazards and precautions associated with processing depleted uranium and methods to control mild radioactivity, chemical toxicity, and pyrophoricity. It also describes the classification and heat treatment of uranium and uranium alloys. Furthermore, the article provides graphical representation of the effect of alloy composition, cooling rate, and aging temperature on microstructure, crystal structure, and mechanical properties of uranium and uranium alloys.
Series: ASM Handbook
Volume: 4E
Publisher: ASM International
Published: 01 June 2016
DOI: 10.31399/asm.hb.v04e.a0006256
EISBN: 978-1-62708-169-6
... Abstract Heat treatment of depleted uranium (DU) alloys with 4.0 wt% or more molybdenum or equivalent is similar to that of dilute alloys. This article discusses the metallurgical characteristics and processing considerations of DU and its alloys, and describes the control of grain size...
Abstract
Heat treatment of depleted uranium (DU) alloys with 4.0 wt% or more molybdenum or equivalent is similar to that of dilute alloys. This article discusses the metallurgical characteristics and processing considerations of DU and its alloys, and describes the control of grain size and orientation using beta treatment. It lists the typical mechanical properties of DU as functions of the amount of cold work and hardness data of uranium rod, and describes the annealing of cold-worked DU. The article also describes the heat treatment of dilute alloys of DU, focusing on the three basic furnace designs used for heating or heat treating of unalloyed uranium: molten salt baths, inert-atmosphere furnaces, and vacuum furnaces. Finally, it presents procedures that are examples of heat treatment used to meet certain specifications of ultimate tensile strength, yield strength, and elongation.
Book: Corrosion: Materials
Series: ASM Handbook
Volume: 13B
Publisher: ASM International
Published: 01 January 2005
DOI: 10.31399/asm.hb.v13b.a0003828
EISBN: 978-1-62708-183-2
... Abstract This article reviews general corrosion of uranium and its alloys under atmospheric and aqueous exposure as well as with gaseous environments. It describes the dependence of uranium and uranium alloy corrosion on microstructure, alloying, solution chemistry, and temperature as well...
Abstract
This article reviews general corrosion of uranium and its alloys under atmospheric and aqueous exposure as well as with gaseous environments. It describes the dependence of uranium and uranium alloy corrosion on microstructure, alloying, solution chemistry, and temperature as well as galvanic interactions between uranium, its alloys, and other metals. The article provides information on the atmospheric corrosion of uranium based on oxidation in dry air or oxygen, water vapor, and oxygen-water vapor mixtures depending upon particular storage conditions. The mechanism and morphology of hydride corrosion of uranium are discussed. The article provides information on environmentally assisted cracking, protective coatings, and surface modification of uranium and its alloys. It also summarizes the environmental, safety, and health considerations for their use.
Series: ASM Handbook
Volume: 9
Publisher: ASM International
Published: 01 December 2004
DOI: 10.31399/asm.hb.v09.a0003780
EISBN: 978-1-62708-177-1
... Abstract This article discusses the principles of physical metallurgy and metallography of depleted uranium. It describes the techniques involved in the preparation of thin foils for transmission electron microscopy and illustrates the resulting microstructure of uranium and uranium alloys...
Abstract
This article discusses the principles of physical metallurgy and metallography of depleted uranium. It describes the techniques involved in the preparation of thin foils for transmission electron microscopy and illustrates the resulting microstructure of uranium and uranium alloys, with the aid of black and white images. The article also provides information on the applications of etching and examination of uranium alloys, at both macro and micro scales, in characterizing the grain structures, segregation patterns, inclusions, and the metal flow geometries produced by solidification and mechanical working processes.
Image
Published: 01 June 2016
Fig. 5 Micrographs showing precipitates in dilute-impurity uranium alloys after beta solution treatment of 730 °C (1345 °F) for 30 min followed by water quenching and an aging treatment. (a) U 3 Si precipitates in a U-400 ppm Si-200 ppm iron alloy after a beta quench followed by an aging
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Published: 01 January 2005
Fig. 8 Corrosion rates as a function of total alloy content for uranium alloys in various chloride-containing solutions exposed to air. Data from Ref 20
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Published: 01 January 2005
Fig. 18 Rate of hydrogen generation versus alloy addition for uranium alloys exposed to 100% RH nitrogen gas at 75 °C (167 °F). Data from Ref 63
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in Uranium and Uranium Alloys
> Properties and Selection: Nonferrous Alloys and Special-Purpose Materials
Published: 01 January 1990
Fig. 10 Stress-strain curve of quenched uranium alloy illustrating initial residual stresses at the surface (A) and interior (B) and how compressive mechanical stress relief reduces residual stress magnitudes
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in Uranium and Uranium Alloys
> Properties and Selection: Nonferrous Alloys and Special-Purpose Materials
Published: 01 January 1990
Series: ASM Desk Editions
Publisher: ASM International
Published: 01 December 1998
DOI: 10.31399/asm.hb.mhde2.a0003166
EISBN: 978-1-62708-199-3
... density materials: depleted uranium and tungsten and their alloys. applications depleted uranium design considerations health considerations mechanical properties metallurgy processing tungsten tungsten alloys uranium alloys very high density metals VERY HIGH DENSITY METALS are used...
Abstract
Very high density materials are used for such applications as counterweights and radiation shields. This article focuses on the metallurgy, processing, properties, fabrication, design considerations, health and safety considerations, and applications of the most commonly used very high density materials: depleted uranium and tungsten and their alloys.
Book Chapter
Book: Alloy Phase Diagrams
Series: ASM Handbook
Volume: 3
Publisher: ASM International
Published: 27 April 2016
DOI: 10.31399/asm.hb.v03.a0006215
EISBN: 978-1-62708-163-4
... Abstract This article is a compilation of binary alloy phase diagrams for which uranium (U) is the first named element in the binary pair. The diagrams are presented with element compositions in weight percent. The atomic percent compositions are given in a secondary scale. For each binary...
Abstract
This article is a compilation of binary alloy phase diagrams for which uranium (U) is the first named element in the binary pair. The diagrams are presented with element compositions in weight percent. The atomic percent compositions are given in a secondary scale. For each binary system, a table of crystallographic data is provided that includes the composition, Pearson symbol, space group, and prototype for each phase.
Image
in Uranium and Uranium Alloys
> Properties and Selection: Nonferrous Alloys and Special-Purpose Materials
Published: 01 January 1990
Fig. 7 Effects of alloy composition on microstructure, crystal structure, and properties of quenched uranium alloys
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Published: 01 December 1998
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in Uranium and Uranium Alloys
> Properties and Selection: Nonferrous Alloys and Special-Purpose Materials
Published: 01 January 1990
Fig. 5 Generalized time-temperature-transformation diagram showing heat treatments employed with uranium alloys. Slow cooling results in diffusional decomposition of γ phase to coarse dual-phase microstructures. Quenching results in diffusionless transformation of γ phase to supersaturated
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Book Chapter
Book: Alloy Phase Diagrams
Series: ASM Handbook
Volume: 3
Publisher: ASM International
Published: 27 April 2016
DOI: 10.31399/asm.hb.v03.a0006199
EISBN: 978-1-62708-163-4
...) Rh-Ti crystallographic data Rh-U (Rhodium-Uranium) Rh-U crystallographic data Rh-V (Rhodium-Vanadium) Rh-V crystallographic data Rh-Zr (Rhodium-Zirconium) Rh-Zr crystallographic data References References 1. Binary Alloy Phase Diagrams , 2nd ed...
Abstract
This article is a compilation of binary alloy phase diagrams for which rhodium (Rh) is the first named element in the binary pair. The diagrams are presented with element compositions in weight percent. The atomic percent compositions are given in a secondary scale. For each binary system, a table of crystallographic data is provided that includes the composition, Pearson symbol, space group, and prototype for each phase.
Image
Published: 01 December 2004
Fig. 21 Casting of a uranium-silicon alloy that contains 3.8% Si. Grains of U 3 Si 2 are surrounded by grains of U 3 Si on a background of a eutectic matrix that is a mixture of uranium and U 3 Si. 500×. See also Fig. 23 in this article. Source: Ref 21
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Published: 01 December 2004
Fig. 22 Same uranium-silicon alloy as Fig. 21 , but the casting has been thermally treated at 900 °C (1650 °F) for several hours. Structure is U 3 Si, within which are contained the remnants of U 3 Si 2 . 500×
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Published: 01 December 2004
Fig. 1 Polymorphism and solubilities of alloying elements in uranium. Note that alloying elements are substantially less soluble in lower temperature phases.
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in Uranium and Uranium Alloys
> Properties and Selection: Nonferrous Alloys and Special-Purpose Materials
Published: 01 January 1990
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