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uranium
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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: 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.
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.
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.
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 January 1986
Fig. 13 Uranium laser-induced fluorescence spectra for a sample found to contain 8 ng U. Individual spectra are offset vertically for clarity; however, the vertical scale is constant. Peak A is the CaF 2 Raman peak; peak B is the uranium fluorescence peak. Spectra are shown for three
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Published: 01 January 1986
Fig. 2 X-ray absorption curve for uranium as a function of wavelength.
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Published: 01 June 2016
Fig. 2 Average grain size of depleted uranium as a function of annealing temperature. 1 h anneals after 50% reduction by rolling at 300 °C (570 °F). A and B are impure metal; C, D, and E are high-purity uranium in decreasing order of submicroscopic inclusion content. Source: Ref 2
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Image
Published: 01 June 2016
Fig. 4 Microstructure of cast depleted uranium refined by beta quenching
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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 June 2016
Fig. 16 Elongation versus hydrogen content for wrought depleted uranium
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Published: 01 June 2016
Fig. 17 Time required to achieve maximum ductility in depleted uranium plate of various thicknesses under a vacuum of 10 −4 torr
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Published: 01 June 2016
Fig. 18 Fixture for solution treating and end quenching of 18 depleted uranium bars
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Published: 01 December 1998
Fig. 1 Effects of composition on structure and properties of quenched uranium alloys
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Published: 01 December 2004
Fig. 20 Portion of the uranium-silicon phase diagram. Source: Ref 21
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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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