Thorex solvent extraction studies with irradiated HTGR fuel: series I

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A series of solvent extraction experiments to test the first-cycle fuel reprocessing flowsheet, proposed by the General Atomic Company for the Hot Engineering Test Facility, was completed. Using irradiated fuel, the experiments were designed to test the extraction, partition, partition-scrub, and strip operations. Each experiment utilized crosscurrent batch extractions and consecutive stages. Each stage was tested in duplicate. Experimental procedures were developed with synthetic feeds and then were used in a hot cell with radioactive solutions of dissolved irradiated fuel. The analytical measurements for thorium and acid compared favorably with the values predicted by the computer program for solvent extraction ... continued below

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Lamb, C.E.; Mitchell, A.D.; Vaughen, V.C.A. & Shannon, R.J. October 1, 1980.

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Description

A series of solvent extraction experiments to test the first-cycle fuel reprocessing flowsheet, proposed by the General Atomic Company for the Hot Engineering Test Facility, was completed. Using irradiated fuel, the experiments were designed to test the extraction, partition, partition-scrub, and strip operations. Each experiment utilized crosscurrent batch extractions and consecutive stages. Each stage was tested in duplicate. Experimental procedures were developed with synthetic feeds and then were used in a hot cell with radioactive solutions of dissolved irradiated fuel. The analytical measurements for thorium and acid compared favorably with the values predicted by the computer program for solvent extraction processes having interacting solutes (SEPHIS-MOD4). The SEPHIS-MOD4 program was valuable in interpreting this first set of experiments with irradiated fuels. Significant problems were experienced in the analysis for uranium in irradiated solutions. These problems emphasize the need for continued development of new or improved procedures for analyzing highly radioactive materials.

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  • Other Information: PBD: Oct 1980

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  • Report No.: ORNL/TM--7108
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/711367 | External Link
  • Office of Scientific & Technical Information Report Number: 711367
  • Archival Resource Key: ark:/67531/metadc708272

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  • October 1, 1980

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  • Sept. 12, 2015, 6:31 a.m.

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  • March 31, 2016, 1:48 p.m.

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Lamb, C.E.; Mitchell, A.D.; Vaughen, V.C.A. & Shannon, R.J. Thorex solvent extraction studies with irradiated HTGR fuel: series I, report, October 1, 1980; Tennessee. (digital.library.unt.edu/ark:/67531/metadc708272/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.