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A Characterization Of Jackson Blue Spring, Jackson County, Florida

Description: Jackson Blue is a first magnitude spring in the karst terrane of northeast Florida. Previous studies have identified inorganic fertilizer as the source of high nitrate levels in the spring. Agricultural land use and karst vulnerability make Jackson Blue a good model for conservation concerns. This work offers an aggregation of studies relating to the springshed, providing a valuable tool for planning and conservation efforts in the region. An analysis of nitrate levels and other water quality parameters within the springshed did not reveal significantly different values between agricultural and forested land use areas. Confounding factors include: high transmissivity in the aquifer, interspersed land use parcels, and fertilizer application in forested areas due to commercial pine stand activity.
Date: December 2011
Creator: Reiser, Cora
Partner: UNT Libraries

Plutonium Nitrate Shipping Investigation

Description: With the AEC complex there has been a long history of shipper-receiver assay differences in the transfer of plutonium nitrate solutions. Since the AEC is considering establishing plutonium nitrate as one of the chemical forms of plutonium for Commission purchase of privately produced plutonium, it is necessary that the shipper-receiver problem be resolved. The program formulated by Rocky Flats for doing this, and the results obtained to date, are discussed. (auth)
Date: September 1, 1963
Creator: Miner, F. J. & Byrne, J. T.
Partner: UNT Libraries Government Documents Department

Effect of composition on the density of multi-component molten nitrate salts.

Description: The density of molten nitrate salts was measured to determine the effects of the constituents on the density of multi-component mixtures. The molten salts consisted of various proportions of the nitrates of potassium, sodium, lithium and calcium. Density measurements ere performed using an Archimedean method and the results were compared to data reported in the literature for the individual constituent salts or simple combinations, such as the binary Solar Salt mixture of NaNO3 and KNO3. The addition of calcium nitrate generally ncreased density, relative to potassium nitrate or sodium nitrate, while lithium nitrate decreased density. The temperature dependence of density is described by a linear equation regardless of composition. The molar volume, and thereby, density of multi-component mixtures an be calculated as a function of temperature using a linear additivity rule based on the properties of the individual constituents.
Date: December 1, 2009
Creator: Bradshaw, Robert W.
Partner: UNT Libraries Government Documents Department

Using Aspen simulation package to determine solubility of mixed salts in TRU waste evaporator bottoms

Description: Nitric acid from plutonium process waste is a candidate for waste minimization by recycling. Process simulation software packages, such as Aspen, are valuable tools to estimate how effective recovery processes can be, however, constants in equations of state for many ionic components are not in their data libraries. One option is to combine single salt solubility`s in the Aspen model for mixed salt system. Single salt solubilities were regressed in Aspen within 0.82 weight percent of literature values. These were combined into a single Aspen model and used in the mixed salt studies. A simulated nitric acid waste containing mixed aluminum, calcium, iron, magnesium and sodium nitrate was tested to determine points of solubility between 25 and 100 C. Only four of the modeled experimental conditions, at 50 C and 75 C, produced a saturated solution. While experimental results indicate that sodium nitrate is the first salt to crystallize out, the Aspen computer model shows that the most insoluble salt, magnesium nitrate, the first salt to crystallize. Possible double salt formation is actually taking place under experimental conditions, which is not captured by the Aspen model.
Date: March 1998
Creator: Hatchell, J. L.
Partner: UNT Libraries Government Documents Department

Equilibrium of the System Lanthanum Nitrate-Praseodymium Nitrate-Nitric Acid-Water-Tributyl Phosphate

Description: A study of the extraction characteristics of the three systems lanthanum nitrate--nitric acid--water--tributyl phosphate, praseodymium nitrate--nitric acid--water--tributyl phosphate, and lanthanum nitrate--praseodymium nitrate nitric acid -water--tributyl phosphate was conducted. The separation factors between praseodymium and lanthanum for the system lanthanum nitrate--praseodymium nitrate-nitric acid--water--tributyl phosphate were shown to be a function of the total nitrate concentration of an equilibrium phase and practically independent of solute composition. A method of predicting the concentrations of lanthanum nitrate, praseodymium nitrate, and nitric acid in an equilibrium phase of the system lanthanum nitrate--praseodymium nitrate--nitric acid--water--tributyl phosphate was presented. A comparison of the extraction characteristics of the system rare-earth nitrate--nitric acid--water--tributyl phosphate for the nitrates of lanthanum, praseodymium, neodymium, and samarium was made. (auth)
Date: November 1, 1960
Creator: Sharp, B. M. & Smutz, M.
Partner: UNT Libraries Government Documents Department

Research and Development Studies on Waste Storage Process

Description: The basic objectives of this program were the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide. To accomplish these objectives, a literature survey was flrst made of available physical and chemical data for the oxides and nitrates of Cs, Sr, Ru, Zr, Nb, and Ce. The data were supplemented by a calculation of thermodynamic functions for RuO/sub 4/ vapor from the experimentally determined infrared spectrum and the theoretically calculated raman-active fundamentals. Data are presented graphically. (C.H.)
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department

PRECISE DETERMINATION OF URANIUM IN URANYL NITRATE-ALUMINUM NITRATE SOLUTIONS

Description: A method was developed for the determination of uranium in aqueous solutions that contain aluminum and in tributyl phosphate. Uranium was separated from aluminum by an ion exchange technique and was then determined gravimetrically by the 8-hydroxyquinoline method. The coefficient of variation was O.3%. (auth)
Date: July 1, 1960
Creator: MacDonald, C.M.
Partner: UNT Libraries Government Documents Department

DECOMPOSITION OF THE TRIBUTYL PHOSPHATE-NITRATE COMPLEXES

Description: Rates of decomposition are reported for the tributyl phosphate complexes of uranyl nitrate and nitric acid under isothermal and adiabatic conditions. These data are used to estimate conditions at which the decomposition reaction becomes self-accelerating. (auth)
Date: November 1, 1960
Creator: Nichols, G.S.
Partner: UNT Libraries Government Documents Department

A COLORIMETER FOR IN-LINE ANALYSIS OF URANIUM AND PLUTONIUM SOLUTIONS

Description: A colorimeter is described that can be used to monitor process solutions continuously for uranyl nitrate or plutonium nitrate concentration. The instrument was tested under plant conditions in the concentration range from 0.1 to 70 grams of uranium per liter and 0.1 to 10 grams of plutonium per liter. The instrument error was plus or minus 1% of the span, but errors of 15 to 20% can be caused by other variables such as acidity and other salts present. (auth)
Date: March 1, 1960
Creator: Colvin, D.W.
Partner: UNT Libraries Government Documents Department

Densities of Ammonium Fluoride-Ammonium Nitrate-Ammonium Hexafluozirconate Solutions

Description: The densities of various Zirflex-type solutions at 25 gas-cooled C can be expressed by the equation: p calc = (0.99710 + 0.03l57 m) + (0.02046 - 0.002659 m)c -(0.0033460.000703 m)c3/2 + 0.14349x + 0.49z where m = moles liter/ sup -1/ NH/sub 4/NO/sub 3/, c = moles liter/sup -1/ NH/sub 4/F, x = moles liter/ sup -1/ (NH/sub 4/)/sub 2/ZrF/sub 6/, and z = moles liter/sup -1/ UO/sub 2/(NO/ sub 3/)/sub 2/. This eq uation fits the data with a sigma value of 0.00018 g/ml for NH/sub 4/FNH/sub 4/NO/sub 3/ solutions, 0.00024 g/ml for NH/sub 4/F-(NH/sub 4/ )/sub 2/ZrF/sub 6/ solutions, and 0.0002 g/ml for solutions containing UO/sub 2/ (NO/sub 3/)/sub 2/ and/or NH/sub 4/F-NH/sub 4/NO/sub 3/ over the range of 0.0M to 6.0M NH/sub 4/F, 0.0M to 1.6M NH/sub 4/NO/sub 3/, 0.0M to 0.5M (NH/sub 4/)/sub 2/ ZrF/sub 6/, and 0.0M to 0.0025M UO/sub 2/(NO/sub 3/)/sub 2/. (auth)
Date: October 27, 1960
Creator: Teague, J. L. & Pearson, D. P.
Partner: UNT Libraries Government Documents Department

EVALUATION OF A REDUCED PRESSURE BACKFLOW PREVENTER USING ACTIVATION ANALYSIS

Description: Despite its advantages of economy and convenience, the reduced-pressure- principle backflow preventer was oniy partialiy accepted as a substitutr for air- gap separation in preventing pollution of potable winter. To evaluate the protection provided by a reduced pressure principle backflow preventer, a unit was tested under the following static conditions; ionic diffusion, lower pressure on the supply side than on the discharge side, vacuum on the supply side, water hammer on the supply side, and water hammer on the discharge side. Using a solution of Mn and K nitrates as a nonradioactive tracer, backflow from the discharge side to the supply side was not detectable by activation and radiochemical analyses having a sensitivity of approximates 0.2 ppb Mn. The protection factor for the device is defined as: P. F. = (Reagent concentration in the discharge zone/ Reagent concentration in the supply zone due to backflow). The minimum protection factor proved in these tests based upon the limit of the sensitivity of Mn analysis is 6.5 x 10/sup 8/. This factor provides a rational basis for inatallation where the concentration of radioactivity or other contaminant can be estimated, measured, or limited. The K analyses also showed no detection of backflow but with a lesser sensitivity. (auth)
Date: January 1, 1963
Creator: Baird, J.N. Jr.; Sanford, W.R. & Cristy, G.A.
Partner: UNT Libraries Government Documents Department

Subcritical measurements with a cylindrical tank of Pu-U nitrate

Description: This series of measurements with a mixed Pu-U nitrate solution (280 g Pu/liter, 180 g U/liter) in a 35.54-cm-diam cylindrical tank provides a wide variety of experimental data for subcritical configurations that can be used to verify calculational methods and nuclear data. The Pu contained 7.85 wt% {sup 240}Pu and the uranium was natural uranium. The measurements performed were: inverse count rate, prompt neutron decay constants, inverse kinetics, and frequency analysis by the {sup 252}Cf source driven method. These data are presented in sufficient detail that the results of the experiments can be calculated directly. For purposes of extrapolating to the delayed critical height the ratio of spectral densities was linear with height and thus provided the best estimate of critical height.
Date: April 1, 1997
Creator: Mihalczo, J.T.; Valentine, T.E. & King, W.T.
Partner: UNT Libraries Government Documents Department

Criticality experiments with mixed plutonium and uranium nitrate solution at a plutonium fraction of 0.4 in slab geometry

Description: R. C. Lloyd of PNL has completed and published a series of critical experiments with mixed plutonium- uranium nitrate solutions (Reference 1). This series of critical experiments was part of an extensive program jointly sponsored by the U. S. Department of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan and was carried out in the mid-1980`s. The experiments evaluated here (published as Report PNL-6327) were performed with mixed plutonium- uranium nitrate solution in a variable thickness slab tank with two 106.7 cm square sides and a width that could be varied from 7.6 to 22.8 cm. The objective of these experiments was to obtain experimental data to permit the validation of computer codes for criticality calculations and of cross-section data to minimize the uncertainties inherent therein, so that facility safety, efficiency, and reliability could be enhanced. The concentrations of the solution were about 105, 293, and 435 g(Pu+U)/liter with a ratio of plutonium to total heavy metal (plutonium plus uranium) of about 0. 40 for all eight experiments. Four measurements were made with a water reflector, and four with no reflector. Following the publication of the initial PNL reports, considerable effort was devoted to an extensive reevaluation of this series of experiments by a collaboration of researchers from ORNL, PNL, and PNC (Reference 2). Their work resulted in a more accurate description of the ``as built`` hardware configuration and the materials specifications. For the evaluations in this report, the data published in Reference 2 by Smolen et al. is selected to supersede the original PNL report. Eight experiments have been evaluated and seven (063, 064, 071, 072, 074, 075, and 076) provide benchmark criticality data. Experiment 073 could not achieve criticality within vessel height limitations.
Date: September 1, 1997
Creator: Pohl, B.A. & Keeton, S.C.
Partner: UNT Libraries Government Documents Department