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Transuranic Decontamination of Nitric Acid Solutions by the Truex Solvent Extraction Process: Preliminary Development Studies

Description: This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solverc (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste.
Date: July 1984
Creator: Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Application of Neutron-Activation Analysis to the Determination of Leach Rates of Simulated Nuclear-Waste Forms

Description: The application of neutron activation analysis to the determination of element release from simulated nuclear waste forms during leaching is described for several different glasses. Potential neutron irradiation effects are discussed, and it is shown, by a series of leach tests on activated and non-activated glass samples, that neutron irradiation has no discernible effect on the release of silicon and cesium during leaching. The radioisotopes best suited for analysis with this method and their… more
Date: February 1982
Creator: Bates, J. K.; Jardine, L. J.; Flynn, K. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Monitoring and Control of TRUEX Processes

Description: The Generic TRUEX Model (GTM) was used to design a flowsheet for the TRUEX solvent extraction process that would be used to determine its instrumentation and control requirements. Sensitivity analyses of the key process variables, namely, the aqueous and organic flow rates, feed compositions, and the number of contactor stages, were carried out to assess their impact on the operation of the TRUEX process. Results of these analyses provide a basis for the selection of an instrument and control s… more
Date: March 1992
Creator: Regalbuto, M. C.; Misra, B.; Chamberlain, D. B.; Leonard, R. A. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiolytic and Thermal Generation of Gases from Hanford Grout Samples : Interim Report

Description: Gamma irradiation of WHC-supplied samples of grouted Tank 102-AP simulated nonradioactive waste has been carried out at three dose rates, 0.25, 0.63, and 130 krad/hr. The low dose rate corresponds to that in the actual grout vaults; with the high dose rate, doses equivalent to more than 40 years in the grout vault were achieved. An average G(H2) = 0.047 molecules/100 eV was found, independent of dose rate. The rate of H2 production decreases above 80 Mrad. For other gases, G(N2) = 0.12, G(O2) =… more
Date: October 1993
Creator: Meisel, Dan; Jonah, Charles D.; Kapoor, S.; Matheson, Max S. & Mulac, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiolytic and Radiolytically Induced Generation of Gases from Synthetic Wastes : Final Report

Description: To better understand the processes leading to the generation and release of gases from waste tanks, the authors studied the radiolytic and thermal generation of H2, N2O, N2, O2, and NH3 in nonradioactive waste simulant solutions and slurries. The radiolytic sources for H2 are e(sub aq)⁻ and its predecessors and H atoms. Radiolysis of the water generates some H2 and an additional amount comes from the hydrogen abstraction reaction H + RH(yields) H2+R(center_dot). Nitrate scavenges e(sub aq)(sup … more
Date: October 1993
Creator: Meisel, Dan; Jonah, Charles D.; Kapoor, S.; Matheson, Max S. & Sauer, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Basic TRUEX Process for Rocky Flats Plant

Description: The Generic TRUEX Model was used to develop a TRUEX process flowsheet for recovering the transuranics (plutonium, americium) from a nitrate waste stream at Rocky Flats Plant. T\
Date: August 1994
Creator: Leonard, R. A.; Chamberlain, D. B.; Dow, J. A.; Farley, S. E.; Nuñez, Luis; Regalbuto, M. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Vibration Model for Centrifugal Contactors

Description: Using the transfer matrix method, we created the Excel worksheet "Beam" for analyzing vibrations in centrifugal contactors. With this worksheet, a user can calculate the first natural frequency of the motor/rotor system for a centrifugal contactor. We determined a typical value for the bearing stiffness (k(sub B)) of a motor after measuring the k(sub B) value for three different motors. The k(sub B) value is an important parameter in this model, but it is not normally available for motors. The … more
Date: November 1992
Creator: Leonard, R. A.; Wasserman, M. O. & Wygmans, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Removal of Fission Products from High Level Radioactive Waste Solutions

Description: Ion exchange, electrolysis, solvent extraction, scavenging and precipitation have been studied as methods for removing radioactive isotopes from high level wastes. Process development has been limited to laboratory research and small scale engineering tests so that the efficiency of these methods in large scale operations is unknown. Emphasis has been placed on removal of Strontium90 and Cesium137 which are the most biologically hazardous of the long lived radioisotopes. Continuous processing o… more
Date: March 30, 1959
Creator: Blanco, R. E. (Raymond Eugene), 1918-1987. & Roberts, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nature of Radioactive Wastes

Description: The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of uranium and thorium fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic n… more
Date: January 26, 1959
Creator: Culler, F. L, Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review and Evaluation of Extractants for Strontium Removal Using Magnetically Assisted Chemical Separation

Description: A literature review on extractants for strontium removal was initially performed at Northern Illinois University to assess their potential in magnetically assisted chemical separation. A series of potential strontium extractants was systematically evaluated there using radioanalytical methods. Initial experiments were designed to test the uptake of strontium from nitric acid using several samples of magnetic extractant particles that were coated with various crown ether ligands. High partition … more
Date: November 1995
Creator: Bauer, C. B.; Rogers, R. D.; Nuñez, Luis; Ziemer, M. D.; Pleune, T. T. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of Plutonium-Bearing Wastes by Chemical Analysis and Analytical Electron Microscopy

Description: This report summarizes the results of characterization studies of plutonium-bearing wastes produced at the US Department of Energy weapons production facilities. Several different solid wastes were characterized, including incinerator ash and ash heels from Rocky Flats Plant and Los Alamos National Laboratory; sand, stag, and crucible waste from Hanford; and LECO crucibles from the Savannah River Site. These materials were characterized by chemical analysis and analytical electron microscopy. T… more
Date: September 1995
Creator: Behrens, R. G.; Buck, E. C.; Dietz, N. L.; Bates, J. K.; Van Deventer, E. & Chaiko, David J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction of Long-Lived Radionuclides from Caustic Hanford Tank Waste Supernatants

Description: A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as Tc-99 and I-129, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO₄⁻ and I⁻ are selectively transferred to the less dense PEG-rich aqueous phase. The partitio… more
Date: July 1995
Creator: Chaiko, David J.; Mertz, C. J.; Vojta, Y.; Henriksen, J. L.; Neff, R. & Takeuchi, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Viscosity and Settling Rates of TBP Waste Metal Slurries as a Function of Shear

Description: This report follows work that is meant to determine the settling rate and viscosity of Hanford Waste metal slurry as a function of prolonged agitation and shear, and to repeat these determinations on a synthetic incubated material similar to that used in the acidification studies, HW-18367, and to make a direct comparison between the genuine and simulated wastes.
Date: January 2, 1951
Creator: Varga, L. P. & Harmon, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination of Dissolver Vent Gases at Hanford

Description: The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.
Date: February 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of the Higgins Continuous Ion Exchange Contactor for the Recovery of Uranium from Leached Ore Pulps

Description: From introduction: "The objective of this report is to present the results and describe the tests of both the 2-in. D and 6-in. D contractors using mill pulp feeds. Work on determining resign attrition is also reported. ORNL-CF-52-12-101 described the results of preliminary tests using synthetic ore pulps."
Date: March 25, 1955
Creator: Higgins, I. R.; Hancher, C. W. & Arehart, T. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee, March 27- 28, 1950; Section 2. Evaporation

Description: Technical report summarizing the waste problems of the Brookhaven National Laboratory site and solutions to problems of nuclear waste evaporation; outline of the second session for the March 27-28, 1950 meeting of the U.S. Atomic Energy Commission Waste Processing Committee at Brookhaven National Laboratory.
Date: 1950
Creator: Hayner, J. H. & Manowitz, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964

Description: Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date: April 15, 1965
Creator: Platt, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Transition Metal Oxide and Mixed-Network Formers on Structure and Properties of Borosilicate Glasses

Description: First, the effect of transition metal oxide (e.g., V2O5, Co2O3, etc.) on the physical properties (e.g., density, glass transition temperature (Tg), optical properties and mechanical properties) and chemical durability of a simplified borosilicate nuclear waste glass was investigated. Adding V2O5 in borosilicate nuclear waste glasses decreases the Tg, while increasing the fracture toughness and chemical durability, which benefit the future formulation of nuclear waste glasses. Second, structural… more
Date: December 2018
Creator: Lu, Xiaonan
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries
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Radiolytic Generation of Gases from Synthetic Waste, Annual Report: 1991

Description: Annual report of an Argonne National Laboratory Chemistry Division program on radiolytic generation of gases from synthetic waste. This report includes results of studies on simulated waste solutions to measure the presence and absence of organic chelators and their products.
Date: December 1991
Creator: Meisel, Dan; Diamond, H.; Horwitz, E. P.; Jonah, Charles D.; Matheson, Max S.; Sauer, M. C., Jr. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Activities in Process Water

Description: The recycling of the process water through the active region of the reactor produces radioactivity in the process water. The source of this radioactivity if (1) activation of dissolved salts in the water, (2) activation of the water itself, (3) activation of the corrosion products, (4) corrosion of active meta and (5) metal recoils from the surface of the reactor. After processes to reduce the radiation level, the activity discharged to the river amounts to 0.468 micro-curie per liter. This all… more
Date: April 7, 1947
Creator: Farmer, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Project AN0115A Annual Report, 1977: Migration of Long-Lived Radioactive Processing Wastes in Selected Rocks

Description: Annual report of Argonne National Laboratory project ANO115A. This report discusses research to compare migration of radionuclides in scale models versus the Pu-Am disposal areas at Los Alamos Laboratory.
Date: 1978?
Creator: Fried, Sherman; Friedman, M. A.; Cohen, Donald; Hines, John & Strickert, Richard G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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