CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, SEPTEMBER 1958

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The feasibility was demonstrated of the use of liquidorganic scintillators in contact with an alpha emitting aqueous phase for the measurement of interfacial area in a mixer. The transpiration flow of pure water reduced the corrosion by a factor of 60 of a porous nickel tube by FeC1/sub 3/. One continuous DRUHM reaction study was made in which poor product consolidation resulted from a less than optimum sodium feed rate. In Fluorox run FBR-19, an over-all material balance of 102% and a UF/sub 6/ balance of 97% was obtained, with a UF/sub 6/ recovery of 71%. The flame denitration of ... continued below

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Pages: 38

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Bresee, J.C.; Haas, P.A.; Watson, C.D. & Whatley, M.E. November 18, 1958.

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Description

The feasibility was demonstrated of the use of liquidorganic scintillators in contact with an alpha emitting aqueous phase for the measurement of interfacial area in a mixer. The transpiration flow of pure water reduced the corrosion by a factor of 60 of a porous nickel tube by FeC1/sub 3/. One continuous DRUHM reaction study was made in which poor product consolidation resulted from a less than optimum sodium feed rate. In Fluorox run FBR-19, an over-all material balance of 102% and a UF/sub 6/ balance of 97% was obtained, with a UF/sub 6/ recovery of 71%. The flame denitration of a thorium-uranium nitrate solution in an oxygen acetylene flame was carried out successfully to produce a mixed oxide of 1.5 micron mean particle size with a surface area of 5.8 m/sup 2/g. Cylindrical hydroclones were tested for the collection of circulating thoria slurries. In the determination of the uranium loading of anion exchange resin a predicted maximum loading at a sulfate concentration of approximately 0.04 M was not found in preliminary experiments. A continuous Darex run was carried out with sections of prototype APPR plates and was frequently interrupted due to the deposition of siliceous material in the stripping column. A Zircex run was carried out with commercially available HCl gas containing oxygen rather than carbon dioxide as the major impurity, resulting in comparable uranium losses due to the formation of aqueous insoluble oxide solids. Simulated "25" waste was evaporated as a neutralized and unneutralized solution, giving condensates which were 0.5 M and 4 M in acid, respectively. (auth)

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Pages: 38

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

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  • Report No.: CF-58-9-62
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4186573 | External Link
  • Office of Scientific & Technical Information Report Number: 4186573
  • Archival Resource Key: ark:/67531/metadc874341

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  • November 18, 1958

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  • Sept. 21, 2016, 2:29 a.m.

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  • Nov. 3, 2016, 6:24 p.m.

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Bresee, J.C.; Haas, P.A.; Watson, C.D. & Whatley, M.E. CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, SEPTEMBER 1958, report, November 18, 1958; Tennessee. (digital.library.unt.edu/ark:/67531/metadc874341/: accessed October 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.