Stress Corrosion and Corrosion Susceptibility of Depleted Uranium -6 W/o Nb PDF Download

Author: R. W. Bacon
Publisher:
ISBN: 9780855181642
Category : Metallurgy
Languages : en
Pages : 40

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Author: Patricia P. Trzaskoma
Publisher:
ISBN:
Category :
Languages : en
Pages : 17

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Considerable experimental work concerning the corrosion rates, stress corrosion behavior, and effects of corrosion on the mechanical properties of depleted uranium alloys has been performed. In this study data for two alloys, DU-0.75 Ti and DU-2 Mo, in three environments have been collected and compared in order to determine whether there are significant differences in their corrosion characteristics and whether these differences warrant a choice of alloy for kinetic energy penetrator applications. In moist air the corrosion rates of the two alloys are low and appear to be of little consequence with respect to this application. In salt fog the corrosion rate of DU-3/4 Ti increases sharply. The weight loss in thirty days is about 7% of the total weight. No data was found for the molybdenum alloy in salt fog. Further experimental work is suggested.

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Category :
Languages : en
Pages :

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The resistance of corrosion and stress-corrosion cracking of welded U--6 wt% Nb in oxygen-saturated water containing 50 ppM chloride ions was investigated. The tests showed that a post-weld heat treatment consisting of solution quenching and underaging (350 deg C for 42 min) provided the best resistance to corrosion and pitting corrosion. Although selective corrosion and pitting corrosion were observed on many of the specimens tested, no evidence of stress-corrosion cracking was found. (auth).

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Languages : en
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The stress corrosion cracking behavior of U-21/4, 41/2, 6 and 8 wt % Nb alloys was evaluated in laboratory air and in aqueous Cl− solutions. Thresholds for crack propagation were obtained in these environments. The data showed that Cl− solutions are more deleterious than air environments. Tests were also conducted in pure gases to identify the species in the air responsible for cracking. These data showed the primary stress corrodent is water vapor for the most reactive alloy, U-21/4% Nb, while O2 is primarily responsible for cracking in the more corrosion resistant alloys, U-6 and 8% Nb. The 41/2% alloy was found to be susceptible in both H2O and O2 environments.

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Languages : en
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Mechanical properties of the uranium-6 wt percent niobium alloy change with aging time and temperature. In general, the ultimate tensile strength and hardness reach a peak, while elongation becomes a minimum at aging temperatures between 400 and 500°C. The first optical evidence of a second phase was in the 400°C-aged alloy, while complete transformation to a two-phase structure was seen in the 600°C-aged alloy. The maximum-strength conditions correlate with the minimum stress corrosion cracking (SCC) resistance. The maximum SCC resistance is found in the as-quenched and 150, 200, and 600$sup 0$C-aged specimens. The as-quenched and 300°C-aged specimens had the greatest resistance to general corrosion in aqueous chloride solutions; the 600°C-aged specimen had the least resistance. (auth).

Author: L. L. Stephenson
Publisher:
ISBN:
Category : Stress corrosion
Languages : en
Pages : 30

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Author: Melvin L. Bleiberg
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 122

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The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed.

Author: Chinhong Chen
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 78

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ISBN:
Category : Power resources
Languages : en
Pages : 1696

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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1162

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