PROCESSING OF HIGH-FIRED URANIUM DIOXIDE FUELS BY A REDUCTION-MERCURY EXTRACTION-OXIDATION PROCESS

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A preliminary flowsheet for the purification of uranium dioxide fuels by a magnesium reduction-- mercury extraction-- steam oxidation process is proposed. Feasibility was indicated by laboratory-scale scouting experiments. Data evaluation indicated 100% reduction of uranium dioxide by magnesium although this figure was not demonstrated, chiefly because of poor choice of materials and design of equipment. Steam oxidation of uranlum tetramercuride produced an oxide with an O/U ratio of 2.43. This ratio was decreased to 2.09 by heating the oxide in a hydrogen atmosphere at 900 deg C for 1 hr. The final product had a surface area of 3.5 m/sup ... continued below

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Pages: 13

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Messing, A. F. & Dean, O. C. August 12, 1960.

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Description

A preliminary flowsheet for the purification of uranium dioxide fuels by a magnesium reduction-- mercury extraction-- steam oxidation process is proposed. Feasibility was indicated by laboratory-scale scouting experiments. Data evaluation indicated 100% reduction of uranium dioxide by magnesium although this figure was not demonstrated, chiefly because of poor choice of materials and design of equipment. Steam oxidation of uranlum tetramercuride produced an oxide with an O/U ratio of 2.43. This ratio was decreased to 2.09 by heating the oxide in a hydrogen atmosphere at 900 deg C for 1 hr. The final product had a surface area of 3.5 m/sup 2//g, and 18% of the panticles were < 1 mu diam. A pellet of the oxide sintered at 1750 deg C had a density of 9.76 g/cc, 89% of theoretical. Decontamination factors demonstrated for ruthenium, cesium, and samarium, when present originally in amounts equivalent to 30,000 Mwd/ton fuel burnup and 60 days' decay, were

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Pages: 13

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

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  • Report No.: ORNL-2909
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4165427 | External Link
  • Office of Scientific & Technical Information Report Number: 4165427
  • Archival Resource Key: ark:/67531/metadc865555

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  • August 12, 1960

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  • Sept. 16, 2016, 12:32 a.m.

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  • Nov. 3, 2016, 6:30 p.m.

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Messing, A. F. & Dean, O. C. PROCESSING OF HIGH-FIRED URANIUM DIOXIDE FUELS BY A REDUCTION-MERCURY EXTRACTION-OXIDATION PROCESS, report, August 12, 1960; Tennessee. (digital.library.unt.edu/ark:/67531/metadc865555/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.