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

Abstract

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 This test was performed on three blanket fuel segments from the ANL-W EBR-II nuclear reactor which were originally made up of depleted uranium (DU).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,more » an investigation is currently being undertaken to both qualify and quantify H{sub 2} formation during uranium spent nuclear fuel corrosion in water.« less

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
754233
Report Number(s):
ANL-99/13
TRN: US0002761
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 3 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; LEACHING; EBR-2 REACTOR; RADIOACTIVE WASTE DISPOSAL; GROUND WATER; STRONTIUM 90; CESIUM 137; URANIUM DIOXIDE; URANIUM HYDRIDES; SPENT FUELS

Citation Formats

Fonnesbeck, J. E. EBR-II blanket fuel leaching test using simulated J-13 well water.. United States: N. p., 1999. Web. doi:10.2172/754233.
Fonnesbeck, J. E. EBR-II blanket fuel leaching test using simulated J-13 well water.. United States. doi:10.2172/754233.
Fonnesbeck, J. E. Fri . "EBR-II blanket fuel leaching test using simulated J-13 well water.". United States. doi:10.2172/754233. https://www.osti.gov/servlets/purl/754233.
@article{osti_754233,
title = {EBR-II blanket fuel leaching test using simulated J-13 well water.},
author = {Fonnesbeck, J. E.},
abstractNote = {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.},
doi = {10.2172/754233},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}