Migration of Uranium Process Wastes from the Uranium-233--Thorium-232 Cycle

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Description

With the advent of fuel loadings of uranium-233 in the Shippingport Reactor, it has become important to understand the migratory behavior of uranium. The purpose of this study is the determination of the parameters influencing the migration of uranium(VI), the most likely chemical form of uranium to be mobilized from a repository. Samples of rhyolite tuff were used to measure the absorption coefficients of solutions of uranium (VI) in ground waters. In addition, columns of tuff were used to measure the elution behavior of uranium (VI) at various conditions of pH, uranium (VI) concentration, and flow saturation. These results indicate ... continued below

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17 p. : charts, photographs

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Fried, Sherman; Sabau, Carmen; Hines, John & Friedman, M. A. 1979?.

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  • Main Title: Migration of Uranium Process Wastes from the Uranium-233--Thorium-232 Cycle
  • Added Title: ANL (Series)
  • Added Title: Argonne National Laboratory Report ANL-78-22
  • Series Title: Argonne National Laboratory Reports

Description

With the advent of fuel loadings of uranium-233 in the Shippingport Reactor, it has become important to understand the migratory behavior of uranium. The purpose of this study is the determination of the parameters influencing the migration of uranium(VI), the most likely chemical form of uranium to be mobilized from a repository. Samples of rhyolite tuff were used to measure the absorption coefficients of solutions of uranium (VI) in ground waters. In addition, columns of tuff were used to measure the elution behavior of uranium (VI) at various conditions of pH, uranium (VI) concentration, and flow saturation. These results indicate that there are several elution peaks with values of Kd between 35 and 120. This behavior is not the same as that of Plutonium(VI) on tuff; and the experimental results to date have not revealed the reason for this difference. Values of Kd in this range imply that geological containment would be difficult in strata of this type. It may be possible to find more retentive strata than tuff. Rocks containing reducing components are the most likely candidates and further investigation is urgently needed if the uranium-233-thorium cycle is to be widely used.

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17 p. : charts, photographs

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  • 1979?

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  • Aug. 4, 2015, 8:33 a.m.

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  • Jan. 11, 2018, 3:39 p.m.

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Fried, Sherman; Sabau, Carmen; Hines, John & Friedman, M. A. Migration of Uranium Process Wastes from the Uranium-233--Thorium-232 Cycle, report, 1979?; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc283613/: accessed October 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.