EBR-II blanket fuel leaching test using simulated J-13 well water.

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Description

This paper discusses the results of a pulsed-flow leaching test using simulated J-13 well water leachant. This test was performed on three blanket fuel segments from the ANL-W EBR-II nuclear reactor which were originally made up of depleted uranium (DU). This experiment was designed to mimic conditions which would exist if, upon disposal of this material in a geological repository, it came in direct contact with groundwater. These segments were contained in pressure vessels and maintained at a constant temperature of 90 C. Weekly aliquots of leachate were taken from the three vessels and replaced with an equal volume of ... continued below

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26 p.

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Fonnesbeck, J. E. September 3, 1999.

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Description

This paper discusses the results of a pulsed-flow leaching test using simulated J-13 well water leachant. This test was performed on three blanket fuel segments from the ANL-W EBR-II nuclear reactor which were originally made up of depleted uranium (DU). This experiment was designed to mimic conditions which would exist if, upon disposal of this material in a geological repository, it came in direct contact with groundwater. These segments were contained in pressure vessels and maintained at a constant temperature of 90 C. Weekly aliquots of leachate were taken from the three vessels and replaced with an equal volume of fresh leachant. These weekly aliquots were analyzed for both {sup 90}Sr and {sup 137}Cs. The results of the pulsed-flow leach test showed the formation of uranium oxide (UO{sub 2}) and uranium hydride (UH{sub 3}) particulate with rapid release of the {sup 137}Cs and {sup 90}Sr to the leachant. On the fifth week of sampling, one of the vessels became over pressurized and vented gas when opened. The most reasonable explanation for the presence of gas in this vessel is that the unoxidized uranium metal in the blanket segment could have reacted with the surrounding water leachant to form hydrogen. However, an investigation is currently being undertaken to both qualify and quantify H{sub 2} formation during uranium spent nuclear fuel corrosion in water.

Physical Description

26 p.

Notes

INIS; OSTI as DE00754233

Medium: P; Size: 26 pages

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  • Other Information: PBD: 3 Sep 1999

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  • Report No.: ANL-99/13
  • Grant Number: W-31109-ENG-38
  • DOI: 10.2172/754233 | External Link
  • Office of Scientific & Technical Information Report Number: 754233
  • Archival Resource Key: ark:/67531/metadc711346

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  • September 3, 1999

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • April 10, 2017, 6:26 p.m.

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Fonnesbeck, J. E. EBR-II blanket fuel leaching test using simulated J-13 well water., report, September 3, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc711346/: accessed September 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.