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Dissolution Of Low Enriched Uo2
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Book Synopsis Dissolution of Low-enriched UO2 by :
Download or read book Dissolution of Low-enriched UO2 written by and published by . This book was released on 1997 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Some conclusions from this report are: (1) A UO2/Al dispersion target can be successfully dissolved in alkaline peroxide solutions; (2) after destruction of the peroxide recovery of the 99Mo would be nearly identical to existing processes using basic dissolution; (3) a low-enriched UO2/Al dispersion targets could potentially be used for the production of 99Mo; and (4) punched cores from a UO2/Al dispersion target will be irradiated to low-level burnup and effects of this LEU target on the recovery of 99Mo will be investigated. A commercial partner will be sought for full scale demonstrations.
Book Synopsis Analysis of UO2 Dissolution in Nitric Acid Solution by : H. F. Johnson
Download or read book Analysis of UO2 Dissolution in Nitric Acid Solution written by H. F. Johnson and published by . This book was released on 1962 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution of Low-enriched UO{sub 2}/Al Dispersion Plates in Alkaline Peroxide Solution by :
Download or read book Dissolution of Low-enriched UO{sub 2}/Al Dispersion Plates in Alkaline Peroxide Solution written by and published by . This book was released on 1997 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Some conclusions from this report are: (1) A UO2/Al dispersion target can be successfully dissolved in alkaline peroxide solutions; (2) after destruction of the peroxide recovery of the 99Mo would be nearly identical to existing processes using basic dissolution; (3) a low-enriched UO2/Al dispersion targets could potentially be used for the production of 99Mo; and (4) punched cores from a UO2/Al dispersion target will be irradiated to low-level burnup and effects of this LEU target on the recovery of 99Mo will be investigated. A commercial partner will be sought for full scale demonstrations.
Book Synopsis Dissolution of Highly Enriched Uranium from the Idaho National Engineering and Environmental Laboratory by :
Download or read book Dissolution of Highly Enriched Uranium from the Idaho National Engineering and Environmental Laboratory written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Since the capability to purify uranium (U) was terminated at the Idaho National Engineering and Environmental Laboratory (INEEL) in the early 1990's, excess highly enriched uranium (HEU) from the cleanout of uranium trioxide (UO3) production equipment will be shipped to the Savannah River Site (SRS) for disposition. The excess material will be dissolved in Phase I of HB-Line, purified by solvent extraction, and blended with normal U to an enrichment which can be used to fabricate fuel for Tennessee Valley Authority (TVA) reactors. The proposed HB-Line processing strategy is to dissolve up to 3 kg of material per 18 L dissolver batch. To demonstrate the proposed processing strategy, two samples of the HEU were shipped to the Savannah River Technology Center (SRTC). The material was used in a series of small-scale experiments in which prototypical amounts were dissolved to characterize the offgas and measure the dissolution time under varying process conditions. Complete dissolution of the U was obtained in 15-30 min for experiments performed at 23-60 degrees Celsius. The HEU was dissolved in 3.5M HNO3 using the solids to liquid ratio proposed for use in HB-Line. The experiment performed at 23 degrees Celsius demonstrated that rapid heat generation during the dissolution is not a concern.
Book Synopsis The Dissolution of Uranium Oxides in HB-Line Phase 1 Dissolvers by :
Download or read book The Dissolution of Uranium Oxides in HB-Line Phase 1 Dissolvers written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Dissolution Characteristics of Mixed UO2 Powders in J-13 Water Under Saturated Conditions by :
Download or read book Dissolution Characteristics of Mixed UO2 Powders in J-13 Water Under Saturated Conditions written by and published by . This book was released on 1991 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Yucca Mountain Project/Spent Fuel program at Argonne National Laboratory is designed to determine radionuclide release rates by exposing high-level waste to repository-relevant groundwater. To gain experience for the tests with spent fuel, a scoping experiment was conducted at room temperature to determine the uranium release rate from an unirradiated UO2 powder mixture (14.3 wt % enrichment in 235U) to J-13 water under saturated conditions. Another goal set for the experiment was to develop a method for utilizing isotope dilution techniques to determine whether the dissolution rate of UO2 matrix is in accordance with an existing kinetic model. Results of these analyses revealed unequal uranium dissolution rates from the enriched and depleted portions of the powder mixture because of undisclosed differences between them. Although the presence of this inhomogeneity has precluded the application of the kinetic model, it also provided an opportunity to elaborate on the utilization of isotope dilution data in recognizing and quantifying such conditions. Detailed listings of uranium release and solution chemistry data are presented. Other problems commonly associated with spent fuel, such as the effectiveness of filtering media, the existence of uranium concentration peaks during early stages of the leach tests, the need for concentration corrections due to water replenishments of sample volumes, and experience derived from isotope dilution data are discussed in the context of the present results. 10 refs., 5 figs., 7 tabs.
Book Synopsis Dissolution Rates of Unirradiated UO2, UO2 Doped with 233U, and Spent Fuel Under Normal Atmospheric Conditions and Under Reducing Conditions Using an Isotope Dilution Method by : Kaija Ollila
Download or read book Dissolution Rates of Unirradiated UO2, UO2 Doped with 233U, and Spent Fuel Under Normal Atmospheric Conditions and Under Reducing Conditions Using an Isotope Dilution Method written by Kaija Ollila and published by . This book was released on 2003 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Kinetics of UO2 Dissolution Under Highly Alkaline Conditions by : Narcís Gay Villaret
Download or read book Kinetics of UO2 Dissolution Under Highly Alkaline Conditions written by Narcís Gay Villaret and published by . This book was released on 2019 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The treatment and management of nuclear waste keeps generating technical and ethical problems nowadays, being one of the most important environmental challenges. Due to this problem, international organizations have seen in the concept of deep geological disposal, materialized in Deep Geological Repository (DGR), the most viable and safe way to give a permanent solution to this problem. Multibarrier containment of DGR will eventually fail and tens or thousands of years later, groundwater,which is the only likely vector that may transport radioisotopes back to the biosphere, may contact the spent nuclear fuel (SNF). Consequently, SNF itself is the last barrier to offer resistance to the action of water. In this project, the effect of cementitious waters, from the construction of DGR, on the kinetics of dissolution of uranium dioxide (UO2) has been studied. UO2 has been used as a chemical analogue of SNF. This type of water leads to highly alkaline conditions with presence of silicate (SiO3 2- ) and calcium (Ca2+ ). Moreover, the influence of carbonate (CO3 2 ) present in groundwater has been studied. A continuous thin film flow-through reactor system has been used for the quantifica.
Book Synopsis Dissolution Mechanism of UO[sub 2] at Various Parametric Conditions by : Kaija Ollila
Download or read book Dissolution Mechanism of UO[sub 2] at Various Parametric Conditions written by Kaija Ollila and published by . This book was released on 1988 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Dissolution Rate of Unirratiated UO2 Under Repository Conditions by : Amanda J. Casella
Download or read book The Dissolution Rate of Unirratiated UO2 Under Repository Conditions written by Amanda J. Casella and published by . This book was released on 2008 with total page 166 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the performance assessments of proposed geologic repositories the effects of temperature, dissolved O2, and water and fuel chemistry on the dissolution rates of spent fuel are necessary to provide a quantitative estimate of the potential dose over geologic time frames. In this research, fuels containing Gd2O3-doped UO2 were tested in a single-pass flow-through setup. These tests have verified that in bicarbonate solutions as temperature increased the dissolution rate increased. However, the presence of silicate in the feedwater altered the system and lowered the dissolution rate at higher temperatures. Only the pure UO2 samples exhibited a dependence on the dissolved O2 concentration, which increased with rising temperature. The Gd2O3-dopant stabilized the fuel matrix and lowered the dissolution rate increasingly up to 4 wt%. The dissolution rates for pure UO2 compared reasonably well with the Yucca Mountain Model for tests performed at 50°C and 75°C, but were found to be approximately half the values predicted by the model at 25°C. After long time periods when the radiolytic field has diminished, additional benefits in dissolution reduction should exist due to constituents such as Gd2O3 in the fuel matrix and silicate in the groundwater. Thus, the durability of spent fuel in Yucca Mountain may be greater than previously modeled.
Book Synopsis Modeling of UO2 Aqueous Dissolution Over a Wide Range of Conditions by :
Download or read book Modeling of UO2 Aqueous Dissolution Over a Wide Range of Conditions written by and published by . This book was released on 1993 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Previously it was not possible to predict reliably the rate at which spent fuel would react with groundwater because of conflicting data in the literature. The dissolution of the UO2 spent fuel matrix is a necessary step for aqueous release of radioactive fission products. Statistical experimental design was used to plan a set of UO2 dissolution experiments to examine systematically the effects of temperature (25--75C), dissolved oxygen (0.002--0.2 atm overpressure), pH (8--10) and carbonate (2-200 x 10−4 molar) concentrations on UO2 dissolution. The average uranium dissolution rate was 4.3 mg/m2/day. The regression fit of the data indicate an Arrhenius type activation energy of 8750 cal/mol and a half-power dependence on dissolved oxygen in the simulated groundwater.
Book Synopsis Interlaboratory Comparison of UO2 Dissolution Rates by :
Download or read book Interlaboratory Comparison of UO2 Dissolution Rates written by and published by . This book was released on 1994 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Direct disposal of spent nuclear fuel in deep underground geologic repositories (vaults) is being pursued by several countries. Isolation relies on multiple barriers consisting of the site geology, engineered barriers including containers to surround the fuel, and the spent fuel itself. These barriers are intended to inhibit dissolution and transport of radionuclides by groundwater, which is virtually the only mechanism available to release radionuclides from the repository. Performance assessment studies are needed to demonstrate the adequacy of the various repository designs. Essential to this performance assessment is an understanding of the dissolution behavior of the spent fuel. Since the dissolution behavior of spent fuel in an actual repository cannot be adequately approximated in a laboratory, laboratory tests and data must be used to develop a mechanistic model that can predict long-term behavior in a repository. Three different laboratories have performed flowthrough dissolution tests at room temperature on portions of the same batch of unirradiated UO2 powder, and good agreement was achieved between the different test results. Dissolution rates obtained from electrochemical studies conducted with UO2 electrodes at Whiteshell Laboratories are compared with the flowthrough test results.
Book Synopsis Mechanisms of leaching and dissolution of uo2 fuel by : M. G. Bailey
Download or read book Mechanisms of leaching and dissolution of uo2 fuel written by M. G. Bailey and published by . This book was released on 1982 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution of unirradiated UO2 and UO2 doped with 233U in low- and high-ionic-strength NaCl under anoxic and reducing conditions by : Kaija Ollila
Download or read book Dissolution of unirradiated UO2 and UO2 doped with 233U in low- and high-ionic-strength NaCl under anoxic and reducing conditions written by Kaija Ollila and published by . This book was released on 2008 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution Characteristics of Mixed UO2 Powders in J-13 Water Under Saturated Conditions by : Ewald Veleckis
Download or read book Dissolution Characteristics of Mixed UO2 Powders in J-13 Water Under Saturated Conditions written by Ewald Veleckis and published by . This book was released on 1991 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Factors affecting the differences in reactivity and dissolution rates between uo2 and spent nuclear fuel by : D. W. Shoesmith
Download or read book Factors affecting the differences in reactivity and dissolution rates between uo2 and spent nuclear fuel written by D. W. Shoesmith and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Induced Dissolution of UO2 by : H. Christensen
Download or read book Radiation Induced Dissolution of UO2 written by H. Christensen and published by . This book was released on 1990 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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