[en] In the field of metallurgy, specifically processes for recovering uranium from wet process phosphoric acid solution derived from the acidulation of uraniferous phosphate ores, problems of imbalance of ion exchange agents, contamination of recycled phosphoric acid with process organics and oxidizing agents, and loss and contamination of uranium product, are solved by removing organics from the raffinate after ion exchange conversion of uranium to uranous form and recovery thereof by ion exchange, and returning organics to the circuit to balance mono and disubstituted ester ion exchange agents; then oxidatively stripping uranium from the agent using hydrogen peroxide; then after ion exchange recovery of uranyl and scrubbing, stripping with sodium carbonate and acidifying the strip solution and using some of it for the scrubbing; regenerating the sodium loaded agent and recycling it to the uranous recovery step. Economic recovery of uranium as a by-product of phosphate fertilizer production is effected. (author)

[en] Dissolved metal values are extracted from a liquid e.g. uranium from phosphoric acid by contacting the liquid with agglomerates for a time to load the agglomerate with the metal value, separating the loaded agglomerates from the liquid phase and stripping the metal value from the loaded agglomerate. The agglomerate may be made by combining finely divided solid particles with a binding liquid to form a paste, adding a suspending liquid to form a mixture, the suspending liquid and binding liquid being immiscible in each other and the solid particles being insoluble in the suspending liquid and shearing the mixture to form the agglomerate. (author)

[en] Steps in the typical pre-conceptual engineering study are: problem identification, identify alternatives, evaluate alternatives, and recommend solution. Three examples of the use of pre-conceptual approach to save money are given; they include the water supply for fire protection in the 200-West Area of Hanford, emergency power for the Purex plant, and new filter for the Purex plant canyon exhaust

[en] A method of fabricating fuel pellets includes apparatus for compacting, granulating, classifying, lubricating and pelletizing the materials is described. The components are arranged below one another, allowing gravity flow, but are offset relative to the preceding stage so that overhead access is provided without interference. (U.K.)

[en] Uranium was extracted with amines dissolved in diluents. Using alamine 336 as an extractant, dodecane as a diluent, and n-octanol as an additive for third phase inhibition, UO₂⁺⁺ extraction from H₂SO₄-Na₂SO₄ aqueous solutions was studied. When the extraction coefficient of uranium was plotted as a function of the initial Na₂SO₄ concentration at a constant sulfuric acid concentration, the typical initial spike type extraction curve was obtained in this case too. Thus, at low Na₂SO₄ concentrations, a reaction such as UO₂SO₄ + 2 (AlamineH)₂SO₄ reversible (AlamineH)₄UO₂(SO₄)₃...(1) is believed to take place, while at high Na₂SO₄ concentrations reaction (2) is thought to be occurring. UO₂(SO₄)₃^4- + 2(R₃NH)₂SO₄ reversible (R₃NH)₄UO₂(SO₄)₃ = 2SO₄^-2...(2). The same result obtained with Na₂SO₄ as with H₂SO₄ is explained by the action of sulfate ions

[en] A method for loading ion exchange resins is described. The process comprises contacting a weak acid cation exchange resin in the ammonium form with a uranyl fluoride salt solution

[en] This document contains responses by the NRC Task Force to comments received on the report ''Environmental Survey of the Reprocessing and Waste Management Portions of the LWR Fuel Cycle'' (NUREG-0116). These responses are directed at all comments, inclding those received after the close of the comment period. Additional information on the environmental impacts of reprocessing and waste management which has either become available since the publication of NUREG-0116 or which adds requested clarification to the information in that document

[en] Results of investigation into certain physicochemical and radiation properties of fluoride wastes resulted from experimental processing of irradiated uranium oxide and uranium-plutonium fuel, as well as behaviour of highly active wastes in the process of their 6-year controlled storage, are presented. Yield of radionuclides into gaseous phase, its composition, leaching rate, thermal and radiation stability, heat conductivity, heat release, compatibility of wastes with structural materials, are determined. An increase in the waste storage time is shown to increase their thermal and radiation stability. Recommendations for the waste storage are given

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No abstract available