Light water reactor fuel reprocessing: dissolution studies of voloxidized and nonvoloxidized fuel

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Small-scale tests with irradiated Zircaloy-clad fuels from Robinson, Oconee, Saxton, and Point Beach reactors with burnups from about 200 to 28,000 MWD/MTHM have been made to determine the dissolution behavior of both voloxidized (U{sub 3}O{sub 8}) and nonvoloxidized (UO{sub 2}) fuel. No significant technical problems were encountered in batch-dissolving of either form. Dissolution rates were well-controlled in all tests. Significant characteristics of U{sub 3}O{sub 8} dissolution that differed from UO{sub 2} dissolution included: (1) reduced tritium and ruthenium ({sup 106}Ru) concentrations in product solutions, (2) increased insoluble noble metal fission product residue (about 2.2X greater), and (3) increased insoluble plutonium ... continued below

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82 p.

Creation Information

Johnson, D.R. & Stone, J.A. April 1, 1980.

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Description

Small-scale tests with irradiated Zircaloy-clad fuels from Robinson, Oconee, Saxton, and Point Beach reactors with burnups from about 200 to 28,000 MWD/MTHM have been made to determine the dissolution behavior of both voloxidized (U{sub 3}O{sub 8}) and nonvoloxidized (UO{sub 2}) fuel. No significant technical problems were encountered in batch-dissolving of either form. Dissolution rates were well-controlled in all tests. Significant characteristics of U{sub 3}O{sub 8} dissolution that differed from UO{sub 2} dissolution included: (1) reduced tritium and ruthenium ({sup 106}Ru) concentrations in product solutions, (2) increased insoluble noble metal fission product residue (about 2.2X greater), and (3) increased insoluble plutonium in the fission product residue. The insoluble plutonium is easily leached from the residue by 10M HNO{sub 3}. The weight of the fission product residue collected from both U{sub 3}O{sub 8} and UO{sub 2} fuels increased aproximately linearly with fuel burnup. A major fraction (>83%) of the {sup 85}Kr was evolved from U{sub 3}O{sub 8} fuel during dissolution rather than voloxidation. The {sup 85}Kr evolution rate was an appropriate monitor of fuel dissolution rate. Virtually all of the {sup 129}I was evolved by air sparging of the dissolver solution during dissolution. 30 tables, 18 figures.

Physical Description

82 p.

Notes

Participants in Fuel Cycle Program. Other requests must be referred to OSTI

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  • Other Information: PBD: Apr 1980

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  • Report No.: DP--1520
  • Grant Number: AC09-76SR00001
  • DOI: 10.2172/711324 | External Link
  • Office of Scientific & Technical Information Report Number: 711324
  • Archival Resource Key: ark:/67531/metadc711069

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  • April 1, 1980

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  • Sept. 12, 2015, 6:31 a.m.

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  • Nov. 29, 2016, 6:31 p.m.

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Johnson, D.R. & Stone, J.A. Light water reactor fuel reprocessing: dissolution studies of voloxidized and nonvoloxidized fuel, report, April 1, 1980; United States. (digital.library.unt.edu/ark:/67531/metadc711069/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.