THE PREPARATION OF URANIUM DIOXIDE FROM A MOLTEN SALT SOLUTION OF URANYL CHLORIDE

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Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas through the mixture. The reaction product, uranyl chloride. was soluble in the molten salt. Although UO/sub 2/ was the most common oxide used, the reaction was similar in the other oxides. Phosgene and aluminum chloride were also used as chlorinating agents. A dense, crystalline precipitate of pure UO/sub 2/ was prepared by the reduction of the uranyl chloride contained in the molten salt solution. The reduction was accomplished by contacting the salt solution with any of several metals, by reaction with hydrogen or dry ammonia ... continued below

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Lyon, W.L. & Voiland, E.E. October 20, 1959.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
    Place of Publication: Richland, Washington

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Description

Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas through the mixture. The reaction product, uranyl chloride. was soluble in the molten salt. Although UO/sub 2/ was the most common oxide used, the reaction was similar in the other oxides. Phosgene and aluminum chloride were also used as chlorinating agents. A dense, crystalline precipitate of pure UO/sub 2/ was prepared by the reduction of the uranyl chloride contained in the molten salt solution. The reduction was accomplished by contacting the salt solution with any of several metals, by reaction with hydrogen or dry ammonia gas, or by electrolysis. Several kilograms of UO/sub 2/ were prepared by electrolysis using graphite electrodes. The physical properties of the material made it potentially useful as a ceramic fuel material. The initial high particle density of the "as-produced" UO/sub 2/ was considered of great potential advantage for adapting this process to the refabrication of irradiated UO/sub 2/ into recycle fuel elements. (M.C.G.)

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: HW-62431
  • Grant Number: AT(45-1)-1350
  • DOI: 10.2172/4150904 | External Link
  • Office of Scientific & Technical Information Report Number: 4150904
  • Archival Resource Key: ark:/67531/metadc865443

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  • October 20, 1959

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Feb. 20, 2017, 4:15 p.m.

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Lyon, W.L. & Voiland, E.E. THE PREPARATION OF URANIUM DIOXIDE FROM A MOLTEN SALT SOLUTION OF URANYL CHLORIDE, report, October 20, 1959; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc865443/: accessed September 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.