Concentration of uranium and plutonium in unsaturated spent fuel tests.

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Commercial spent fuel is being tested under oxidizing conditions at 90 C in drip tests with simulated groundwater to evaluate its long-term performance in a potential repository at Yucca Mountain [1-4]. The tests allow us to monitor the dissolution behavior of the spent fuel matrix and the release rates of individual radionuclides. This paper reports the U and Pu concentrations in the leachates of drip tests during 3.7 years of reaction. Changes in these concentrations are correlated with changes in the measured pH and the appearance of alteration products on the fuel surface. Although there is little thermodynamic information at ... continued below

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10 p.

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Finn, P. A. April 15, 1998.

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Description

Commercial spent fuel is being tested under oxidizing conditions at 90 C in drip tests with simulated groundwater to evaluate its long-term performance in a potential repository at Yucca Mountain [1-4]. The tests allow us to monitor the dissolution behavior of the spent fuel matrix and the release rates of individual radionuclides. This paper reports the U and Pu concentrations in the leachates of drip tests during 3.7 years of reaction. Changes in these concentrations are correlated with changes in the measured pH and the appearance of alteration products on the fuel surface. Although there is little thermodynamic information at 90 C for either uranyl or plutonium compounds, some data are available at 25 C [5-8]. The literature data for the U and Pu solubilities of U and Pu compounds were compared to the U and Pu concentrations in the leachates. We also compare Wilson's [9] U and Pu concentrations in semi-static tests at 85 C on spent fuel with our results.

Physical Description

10 p.

Notes

INIS; OSTI as DE00010740

Medium: P; Size: 10 pages

Source

  • 3rd Topical Meeting on DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998

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  • Report No.: ANL/CMT/CP-96157
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10740
  • Archival Resource Key: ark:/67531/metadc628567

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • April 15, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 6:41 p.m.

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Finn, P. A. Concentration of uranium and plutonium in unsaturated spent fuel tests., article, April 15, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc628567/: accessed December 12, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.