Analysis of UO2 Dissolution in Nitric Acid Solution PDF Download
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Author: H. F. Johnson
Publisher:
ISBN:
Category : Dissolution
Languages : en
Pages : 42
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Author: H. F. Johnson
Publisher:
ISBN:
Category : Dissolution
Languages : en
Pages : 42
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
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A series of characterization and dissolution studies has been performed to define flowsheet conditions for the dissolution of uranium oxide materials in dissolvers. The samples selected for analysis were uranium oxide materials. The selection of these uranium oxide materials for characterization and dissolution studies was based on high enriched uranium content and trace levels of plutonium. Test results from the characterization study identified ferric oxide (Fe2O3) and iron/chromium/nickel (Fe/Cr/Ni) particles as impurities along with the tri-uranium oxide (U3O8) and uranium trioxide (UO3). The weight percent uranium in this material was found to vary depending on the impurity content. The trace impurity plutonium appears to be associated with the Fe/Cr/Ni particles. A small amount of absorbed moisture and waters of hydration is present. Most of the uranium oxides easily dissolved in low-molar nitric acid solutions without fluoride within one to two hours at solution temperature s between 60-80 degrees C.A small amount of residue remained following this dissolution step. To assure complete dissolution of uranium from these oxide materials, an additional dissolution step at 90 degrees C to boiling for at least one to two hours has been suggested. Only trace amounts of iron associated with Fe2O3 and Fe/Cr/Ni particles will dissolve during the dissolution steps. Neither hydrogen nor heat will be generated during the dissolution of these uranium oxide materials in nitric acid solutions. Some brown nitrogen dioxide (NO2) fumes will be generated during the dissolution of U3O8.
Author: J. H. Goode
Publisher:
ISBN:
Category : Nitric acid
Languages : en
Pages : 34
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Author: Armando L. Uriarte
Publisher:
ISBN:
Category : Inorganic acids
Languages : en
Pages : 90
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Author: H.A. Ohlgren, Lee Chajson, K.S. Sanvordenker
Publisher:
ISBN:
Category :
Languages : en
Pages : 17
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Author: D. Herrmann
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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The primary goal of this investigation was to evaluate the effectiveness of the chop-leach process, with nitric acid solvent, to produce a nominally 300 g/L [U] and 1 M [H] product solution. The results of this study show that this processing technique is appropriate for applications in which a low free acid and moderately high U content are desired. The 7.75 L of product solution, which was over 450 g/L in U, was successfully diluted to produce about 13 L of solvent extraction feed that was 302 g/L in U with a [H] in the range 0.8-1.2 M.A secondary goal was to test the effectiveness of this treatment for the removal of actinides from Zircaloy cladding to produce a low-level radioactive waste (LLW) cladding product. Analysis of the cladding shows that actinides are present in the cladding at a concentration of about 5000 [eta]Ci/g, which is about 50 times greater than the acceptable transuranium element limit in low level radioactive waste. It appears that the concentration of nitric acid used for this dissolution study (initial concentration 4 M, with 10 M added as the dissolution proceeded) was inadequate to completely digest the UO2 present in the spent fuel. The mass of insoluble material collected from the initial treatments with nitric acid, 340 g, was much higher than expected, and analysis of this insoluble residue showed that it contained at least 200 g U.
Author:
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ISBN:
Category : Electrolytic oxidation
Languages : en
Pages : 28
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 886
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Author: Muhammad Shabbir
Publisher:
ISBN:
Category : Chemical kinetics
Languages : en
Pages :
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