SOME EFFECTS OF RADIATION ON SOLVENT EXTRACTION PROCESSES

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Presented at the 135th National Meeting of the A.C.S., Boston, April 5- 10, 1959. The yield of total acid, G/sub acid/, in the radiolysis of tributyl phosphate--Amsco 125-82 solutions is 2.7 times the electron fraction of TBP, or approximately 2.7 times the weight fraction of TBP, per 100 ev of energy absorbed by the solution. Dibutyl phosphoric acid, DBPA, constitutes about 85% of the acid. Radiolysis of TBP also results in the conversion of about 0.9 molecules of TBP to a polymer per 100 ev of energy absorbed. Uranium extraction-stripping tests with an 8 stage spinner column have shown that ... continued below

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Pages: 14

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Davis, W. Jr. & Wagner, R.M. January 26, 1959.

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Presented at the 135th National Meeting of the A.C.S., Boston, April 5- 10, 1959. The yield of total acid, G/sub acid/, in the radiolysis of tributyl phosphate--Amsco 125-82 solutions is 2.7 times the electron fraction of TBP, or approximately 2.7 times the weight fraction of TBP, per 100 ev of energy absorbed by the solution. Dibutyl phosphoric acid, DBPA, constitutes about 85% of the acid. Radiolysis of TBP also results in the conversion of about 0.9 molecules of TBP to a polymer per 100 ev of energy absorbed. Uranium extraction-stripping tests with an 8 stage spinner column have shown that one mole of uranium is retained in the organic phase during the stripping operation per mole of DBPA added prior to the extraction operation. This is at least twice as much uranium as would be expected on the basis of a compound of the composition UO/sub 2/(DBP)/ sub 2/. On the basis of a tentative molecular weight of 843 g/mole, the polymer retains in the organic phase during stripping operations about 1.2 moles of uranium per mole of polymer added prior to extraction. In additioo to polymer and acids, condensed phase radiolysis products include olefins, whose yield, expressed as G/sub c=c/, or number of double bonds formed per 100 ev of energy absorbed, decreases from ca 4 to 1 as the TBP concentration increases from 4.5 to 100 wt.%. Among newer extractants being examined for use in radiochemical reprocessing, diethyl carbonate, DEC, has been tested for uranium retention and fission product decontamination properties. After irradiation to the 400 watt-hr/ liter level, the uranium retention by DEC on stripping is decreased, rather than increased. Although gamma -decontamination was adversely affected, BETA - decontamination was essentially unaffected by irradiation to this level. (auth)

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Pages: 14

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  • Other Information: Presented at the 135th National Meeting of the A.C.S., Boston, April 5-10, 1959. Orig. Receipt Date: 31-DEC-59

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  • Report No.: CF-59-1-90(Rev.)
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4238340 | External Link
  • Office of Scientific & Technical Information Report Number: 4238340
  • Archival Resource Key: ark:/67531/metadc1018934

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  • January 26, 1959

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  • Oct. 15, 2017, 10:09 p.m.

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  • Oct. 23, 2017, 6:16 p.m.

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Davis, W. Jr. & Wagner, R.M. SOME EFFECTS OF RADIATION ON SOLVENT EXTRACTION PROCESSES, report, January 26, 1959; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc1018934/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.