Dissolution Kinetics of Nuclear Fuels 1. Uranium

Kindlimann, L. E.; Greene, N. D.

doi:10.5006/0010-9312-23.2.29

Cited by 6 publications

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“…However, the mechanism for the dissolution is not clear. Halide ions in general are known to accelerate the dissolution of metals (Kindlimann and Green, 1967;Kolotyrkin, 1961). In investigation of the dissolution of zirconium in nitric acid containing hydrofluoric acid (DeCrescente et al, 1960;Meyer, 1965;Smith and Hill, 1958;Vander Wall and Whitener, 1959) it was found, for instance, that the rate of dissolution increased with an increase in the hydrofluoric acid concentration, just as with plutonium.…”

Section: Resultsmentioning

confidence: 99%

Dissolution of Plutonium in Dilute Nitric Acid

Miner¹,

Nairn²,

Berry³

1969

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that no ionic mechanism for the rate-determining step is indicated. The failure of stirring to alter the solution rate suggests that the process is not limited by any redox potentials existing in the immediate vicinity of the electrode.The kinetics for the initial dissolution process may be represented by the equation:where the rate constant, ho, depends only on the fading agent employed. I n the second stage the rate constant decreases with tkiickness and therefore with D -D2where h is a function of (D -D2). I t follows from Equation 1 that ho is given by the first column of Table I. Integration of Equation 2 gives:

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Section: Resultsmentioning

confidence: 99%

Dissolution of Plutonium in Dilute Nitric Acid

Miner¹,

Nairn²,

Berry³

1969

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“…Thus, the corrosion rate of Tuba lloy in aqueous solutions is dependent on pH and not on the other ionic species present under the conditions of the experiments by Baker, Less, and Orman. However, using an electrochemical technique, Kindlimann and Greene 10 found that the addition of chloride ions to sulfuric acid increased the dissolution rate of uranium at all potentials and caused shallow pits on the Tuballoy surface. They noted that the dissolution of 'l'uballoy in nitric and sulfuric acids was unusual in that, unlike most metals, the dissolution of uranium is retarded as the acid concentration is increased.…”

Section: Rfp-1586mentioning

confidence: 99%

CORROSION BEHAVIOR OF URANIUM-BASE U--Nb, U--Nb--Zr, AND U--Mo ALLOYS IN HYDROCHLORIC ACID AND OCEAN WATER.

Macki¹,

Kochen²

1971

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“…The applications of metallic uranium are severely limited due to its terrible anti-corrosion properties, low yield strength and low hardness. However, alloying of uranium could overcome these disadvantages, as it has wide applications in the nuclear industry [1,2]. In comparison with other uranium alloy, uranium-titanium alloy could significantly improve the mechanical properties as well as anti-corrosion properties by adding much less alloying element, making it receive wide applications in the nuclear energy industry and military field [3][4][5][6][7].…”

Section: Introductionmentioning

confidence: 99%

Influences of pH Values’ Changes on the Oxide Film of U-0.79 wt.% Ti Alloy in Aqueous Solution—A Combined Study of Traditional Electrochemical Tests and Scanning Reference Electrode Technique

et al. 2019

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By combining traditional electrochemical tests including Tafel extension method and Mott-Schottky fitting, spectroscopic ellipsometry (SE) and a micro-region analysis technique, which is an integrated system of a scanning reference electrode technique and scanning tunneling microscope (SRET/STM), the changes in properties of the oxide film that formed on the surface of the U-0.79 wt.% Ti alloy (U-Ti alloy in short) in 0.1 M NaNO3 were carefully investigated as the pH value changed. The results show that the properties of the oxide film are strongly pH-dependent. The corrosion potential and corrosion current density decrease with the increasing pH value. The oxide film appears to be a p-type semiconductor at pH = 2.43. However, the transition from n-type to p-type for the oxide film as a semiconductor is observed with the increasing applied potential when the solution pH value varies from 2.43 to 7.0. The oxide film presents as an n-type semiconductor when the pH value varies from 7.0 to 11.44. In addition, during the transition of the pH, the roughness and the number of active points of the alloy surface decreases while the oxide film is thicker. It can be concluded that the corrosion resistance of the oxide film formed on the U-Ti alloy surface is enhanced in neutral or alkaline solutions.

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Dissolution Kinetics of Nuclear Fuels 1. Uranium

Cited by 6 publications

References 0 publications

Dissolution of Plutonium in Dilute Nitric Acid

Dissolution of Plutonium in Dilute Nitric Acid

CORROSION BEHAVIOR OF URANIUM-BASE U--Nb, U--Nb--Zr, AND U--Mo ALLOYS IN HYDROCHLORIC ACID AND OCEAN WATER.

Influences of pH Values’ Changes on the Oxide Film of U-0.79 wt.% Ti Alloy in Aqueous Solution—A Combined Study of Traditional Electrochemical Tests and Scanning Reference Electrode Technique

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