A rapid and specific titrimetric method for the precise determination of uranium using iron(II) sulphate as reductant

Davies, Walter

doi:10.1016/0039-9140(64)80171-5

Cited by 401 publications

(109 citation statements)

References 2 publications

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“…1 Since the late 1970s, researchers at ORNL have studied and fully developed the internal gelation process for making UO 2 , (U,Pu)O 2 , ThO 2 , and (UO 2 + UC 2 ) microspherical fuels. [2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18] The internal gelation process used is one of the sol-gel processes developed for the preparation of microspheres of nuclear fuel in which chilled clear broth droplets containing acid-deficient uranyl nitrate (ADUN), hexamethylenetetramine (HMTA), and urea are heated causing homogenous gelation and solidification of the droplets that, after washing treatments, can be dried calcined, and sintered to ceramic kernels of the required density. In the 1990s, ORNL researchers extended the boundaries of the technology by developing the process to make hydrous metal oxide spheres of Ti, Zr, Fe, and other cations for such uses as sorbents, waste forms, catalysts, getters, and dielectrics.…”

Section: Internal Gelation Process and Its Chemistrymentioning

confidence: 99%

Production of Depleted UO<sub>2</sub>Kernels for the Advanced Gas-Cooled Reactor Program for Use in TRISO Coating Development

Collins¹

2004

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Section: Internal Gelation Process and Its Chemistrymentioning

confidence: 99%

Production of Depleted UO<sub>2</sub>Kernels for the Advanced Gas-Cooled Reactor Program for Use in TRISO Coating Development

Collins¹

2004

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“…The uranium content in the stock solution was estimated either by a redox titrimetric or spectrophotometric method, depending on the concentration. 13,14 A stock solution of ruthenium nitrosyl trinitrate (18 g/L supplied by M/s. Arora Matthey, Kolkata) was diluted and used in this study.…”

Section: Chemicals and Reagentsmentioning

confidence: 99%

Sequential Determination of Free Acidity and Plutonium Concentration in the Dissolver Solution of Fast-Breeder Reactor Spent Fuels in a Single Aliquot

Dhamodharan

Pius

2016

ANAL. SCI.

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A simple potentiometric method for determining the free acidity without complexation in the presence of hydrolysable metal ions and sequentially determining the plutonium concentration by a direct spectrophotometric method using a single aliquot was developed. Interference from the major fission products, which are susceptible to hydrolysis at lower acidities, had been investigated in the free acidity measurement. This method is applicable for determining the free acidity over a wide range of nitric acid concentrations as well as the plutonium concentration in the irradiated fuel solution prior to solvent extraction. Since no complexing agent is introduced during the measurement of the free acidity, the purification step is eliminated during the plutonium estimation, and the resultant analytical waste is free from corrosive chemicals and any complexing agent. Hence, uranium and plutonium can be easily recovered from analytical waste by the conventional solvent extraction method. The error involved in determining the free acidity and plutonium is within ±1% and thus this method is superior to the complexation method for routine analysis of plant samples and is also amenable for remote analysis.

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“…The amount of U and U(IV) in a sample can be determined by Davies-Gray titration (Jarabek 1984, Davies and Gray 1964, Eberle and Lemer 1971. The Davies-Gray analyses reported in this work were performed by Materials and Chemistry Laboratory, Inc., of Oak Ridge, Tennessee, using the method described by Jarabek (1984), which is a modification of the method originally reported by Davies and Gray (1964).…”

Section: Davies-gray Titrationmentioning

confidence: 99%

“…The Davies-Gray analyses reported in this work were performed by Materials and Chemistry Laboratory, Inc., of Oak Ridge, Tennessee, using the method described by Jarabek (1984), which is a modification of the method originally reported by Davies and Gray (1964). The method used is described in the following paragraphs.…”

Section: Davies-gray Titrationmentioning

confidence: 99%

Radiolytic Effects on Fluoride Impurities in a U{sub 3}O{sub 8} Matrix

Icenhour¹

2000

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The safe handling and storage of radioactive materials require an understanding of the effects of radiolysis on those materials. Radiolysis may result in the production of gases (e.g., corrosives) or pressures that are deleterious to storage containers. A study has been performed to address these concerns as they relate to the radiolysis of residual fluoride compounds in uranium oxides. The interactions of radiation with crystalline solids, based on the bonding characteristics of the crystal, are described to enhance the understanding of radiolytic effects in uranium oxides. Samples of U02F2wH20 and U~08 (with -1.4 wt YO fluorine content) were irradiated in a 'Co source and in spent nuclear fiel (SNF) elements from the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. Container pressures were monitored &roughout the irradiations, and gas and solid samples were analyzed after the irradiations. The irradiation of U02F2~xH20 produced 02-with G(02)-values ranging from 0.007 to 0.03 molecules 02 produced per 100 eV. Neither F2 nor HF was produced by the irradiations. Chemical analysis of solid samples showed that some of the uranium was reduced from U(W) to U(IV). A saturation damage limit for the U02F2SXH20was demonstrated by using the HFIR SNF elements, and the limit was found to be 7-9°/0(at -108 radlh). It is shown that the covalently bonded oxygen is more susceptible to radiation darnage than is the ionically bonded fluorine. Irradiation of U@8 (with -1.4 wt 'XO fluorine content) resulted in neither gas production nor a pressure increase. These experiments led to the conclusion that U@8 is safe during 10ng-tem'Istorage fiOm overpressurization and the production of corrosives caused by gamma radiolysis of residual fluorides.

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A rapid and specific titrimetric method for the precise determination of uranium using iron(II) sulphate as reductant

Cited by 401 publications

References 2 publications

Production of Depleted UO<sub>2</sub>Kernels for the Advanced Gas-Cooled Reactor Program for Use in TRISO Coating Development

Production of Depleted UO<sub>2</sub>Kernels for the Advanced Gas-Cooled Reactor Program for Use in TRISO Coating Development

Sequential Determination of Free Acidity and Plutonium Concentration in the Dissolver Solution of Fast-Breeder Reactor Spent Fuels in a Single Aliquot

Radiolytic Effects on Fluoride Impurities in a U{sub 3}O{sub 8} Matrix

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