Status and Future Program of Homogeneous Reactor Fuel Processing Studies

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The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress. Rare earth solubility levels and thus poison fraction from this group will be measured after the addition of signiflcant quantities of four important elements has minimized analytical detection problems. The role of ... continued below

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5 p.

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Burch, W. D.; Haas, P. A. & McNees, R. A. June 17, 1959.

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Description

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress. Rare earth solubility levels and thus poison fraction from this group will be measured after the addition of signiflcant quantities of four important elements has minimized analytical detection problems. The role of the tellurium precursor in the interpretation of iodine behavior will be eximined extensively in the present run in an effort to resolve previous discrepancies. Studies of iodine behavior can be continued after shutdown of the hydroclone system if required. An electrolytic process for removal of nickel from fuel solution has been developed through the laboratory and engineering scale except for the design and testing of a cell suitable for radioactive environments. (auth)

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5 p.

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

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  • Report No.: CF-59-6-74
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4164972 | External Link
  • Office of Scientific & Technical Information Report Number: 4164972
  • Archival Resource Key: ark:/67531/metadc872567

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • June 17, 1959

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Oct. 10, 2017, 9:20 p.m.

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Burch, W. D.; Haas, P. A. & McNees, R. A. Status and Future Program of Homogeneous Reactor Fuel Processing Studies, report, June 17, 1959; Tennessee. (digital.library.unt.edu/ark:/67531/metadc872567/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.