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U-0.8Ti
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Effect of quench rate on the microstructure of a U-0.8Ti alloy as seen in b...
Available to PurchasePublished: 01 June 2016
Fig. 8 Effect of quench rate on the microstructure of a U-0.8Ti alloy as seen in bright-field and polarized light optical micrographs. (a) 100% α′ martensite microstructure for a quench rate >400 °C/s (>720 °F/s). (b) Microstructure developed at a cooling rate of ∼360 °C/s (∼650 °F/s
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Residual stresses measured by a neutron diffraction technique in a U-0.8Ti ...
Available to PurchasePublished: 01 June 2016
Fig. 10 Residual stresses measured by a neutron diffraction technique in a U-0.8Ti alloy cylinder. (a) After a gamma solution heat treatment and water immersion quench, a biaxial stress state is observed with very large surface compressive and interior tensile residual stresses. (b) Aging
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Effect of hydrogen content and strain rate on the ductility of a convention...
Available to PurchasePublished: 01 June 2016
Fig. 7 Effect of hydrogen content and strain rate on the ductility of a conventional tensile test for the U-0.8Ti alloy. RA, reduction in rate; TE, total elongation in 16.3 mm (0.64 in.) gage length
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A poorly transformed microstructure developed by a sluggish quench can resu...
Available to PurchasePublished: 01 June 2016
Fig. 9 A poorly transformed microstructure developed by a sluggish quench can result in a quench crack for the U-0.8Ti alloy. Acicular needles are the desired α′ martensite microstructure, while the grayish regions are the undesirable equilibrium α + δ microstructure.
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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
... properties (less scatter) are best obtained when H 2 levels are maintained at 0.1 ppm or less. Erratic ductile behavior in U-0.8Ti can be offset by controlling the effects of hydrogen by reducing the internal hydrogen content from 0.36 to 0.02 ppm H 2 and testing in dried air containing less than 10...
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 Chapter
Corrosion of Uranium and Uranium Alloys
Available to PurchaseBook: 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
... is present or is generated during corrosion, UH 3 can form. Additionally, aqueous electrochemical polarization can produce UH 3 directly or hydrated UO 3 . At temperatures above about 200 °C (390 °F), U 3 O 8 becomes the primary corrosion product. Similar to the group IV metals, uranium forms colorful...
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.