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Mixed waste treatment with a mediated electrochemical process

Description: The process described in this paper is intended to convert mixed waste containing toxic organic compounds (not heavy metals) to ordinary radioactive waste, which is treatable. The process achieves its goal by oxidizing hydrocarbons to CO{sub 2} and H{sub 2}O. Other atoms that may be present in the toxic organic generally are converted to nonhazardous anions such as sulfate and phosphate. This electro chemical conversion is performed at conditions of temperature and pressure that are just modera… more
Date: May 17, 1991
Creator: Hickman, R. G.; Gray, L. W. & Chiba, Z.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Exploratory research, Tasks A, B, C, and D. Final report, August 17-December 31, 1977

Description: SRI International has conducted research on the upgrading of computerized thermo-hydro code calculations and the synthesis of energetic materials. This project comprised four tasks, as follows: Task A included: (1) formulating routines for inverting the P = P(T,V) and V = V(T,P) equations of state when isotherms exhibit a van der Waals' loop; (2) incorporating these routines into the TIGER code so V and T can be used as independent variables in computing thermodynamic functions of liquids exhib… more
Date: February 17, 1978
Creator: Simon, Robert L.; Coon, Clifford L.; Cowperthwaite, Michael & Sincich, Eugene
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Department report on Production Test No. 313-58-M: Recovery of lead dipped slugs

Description: A number of slugs have been dipped in lead, then Al-Si and canned. Laboratory experiments showed that the can and outer bonding layers could be removed by the standard caustic-nitrate treatment. The alloy layer was removed from several slugs by hot nitric acid without use of hydrofluoric acid. It was desired to extend the method to the plant process and to clean accumulated lead dipped pieces. Lead dipped slugs may be cleaned by the regular recovery process with a weight loss of about 0.03 lbs.… more
Date: January 17, 1945
Creator: Eubank, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The SX Solver: A Computer Program for Analyzing Solvent-Extraction Equilibria: Version 3.0

Description: A new computer program, the SX Solver, has been developed to analyze solvent-extraction equilibria. The program operates out of Microsoft Excel and uses the built-in Solver function to minimize the sum of the square of the residuals between measured and calculated distribution coefficients. The extraction of nitric acid by tributyl phosphate has been modeled to illustrate the programs use.
Date: January 17, 2002
Creator: Lumetta, Gregg J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RAPID METHOD FOR DETERMINATION OF RADIOSTRONTIUM IN EMERGENCY MILK SAMPLES

Description: A new rapid separation method for radiostrontium in emergency milk samples was developed at the Savannah River Site (SRS) Environmental Bioassay Laboratory (Aiken, SC, USA) that will allow rapid separation and measurement of Sr-90 within 8 hours. The new method uses calcium phosphate precipitation, nitric acid dissolution of the precipitate to coagulate residual fat/proteins and a rapid strontium separation using Sr Resin (Eichrom Technologies, Darien, IL, USA) with vacuum-assisted flow rates. … more
Date: July 17, 2008
Creator: Maxwell, S. & Culligan, B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of Eliminating Mercury Removal Pretreatment on the Performance of a High Level Radioactive Waste Melter Offgas System

Description: The Defense Waste Processing Facility at the Savannah River Site processes high-level radioactive waste from the processing of nuclear materials that contains dissolved and precipitated metals and radionuclides. Vitrification of this waste into borosilicate glass for ultimate disposal at a geologic repository involves chemically modifying the waste to make it compatible with the glass melter system. Pretreatment steps include removal of excess aluminum by dissolution and washing, and processing… more
Date: March 17, 2009
Creator: Zamecnik, J. & Alexander Choi, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DISSOLUTION OF IRRADIATED MURR FUEL ASSEMBLIES

Description: A literature survey on the dissolution of spent nuclear fuel from the University of Missouri Research Reactor (MURR) has been performed. This survey encompassed both internal and external literature sources for the dissolution of aluminum-clad uranium alloy fuels. The most limiting aspect of dissolution in the current facility configuration involves issues related to the control of the flammability of the off-gas from this process. The primary conclusion of this work is that based on past disso… more
Date: June 17, 2010
Creator: Kyser, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparative Metagenomics of Freshwater Microbial Communities

Description: Previous analyses of a microbial metagenome from uranium and nitric-acid contaminated groundwater (FW106) showed significant environmental effects resulting from the rapid introduction of multiple contaminants. Effects include a massive loss of species and strain biodiversity, accumulation of toxin resistant genes in the metagenome and lateral transfer of toxin resistance genes between community members. To better understand these results in an ecological context, a second metagenome from a pri… more
Date: May 17, 2010
Creator: Hemme, Chris; Deng, Ye; Tu, Qichao; Fields, Matthew; Gentry, Terry; Wu, Liyou et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cesium Eluate Semi-Batch Evaporation Performance

Description: The baseline flowsheet for low activity waste (LAW) in the Hanford River Protection Project (RPP) Waste Treatment Plant (WTP) includes pretreatment of supernatant by removing cesium using ion exchange. When the ion exchange column is loaded, the cesium will be eluted with a 0.5M nitric acid (HNO3) solution to allow the column to be conditioned for re-use. The cesium eluate solution will then be concentrated in a vacuum evaporator to minimize storage volume and to recycle HNO3.
Date: June 17, 2003
Creator: Pierce, Robert A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compatibility Studies of Anion Exchange Resins. Part I. The Compatibility of Dowex 1 X 4 Nitrate Form Anion Resin With Nitric Acid and Oxides of Nitrogen

Description: The compatibility of Dowex 1x4 nitrate form anion resin with nitric acid, and the compatibility of several types of plastic tubing with nitric acid were investigated. Ignition properties of resin extract, treated resin and mixtures of tubing extract with either resin extract or treated resin were also investigated.
Date: May 17, 1965
Creator: Molen, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OXIDATION OF PLUTONIUM (III) BY SODIUM NITRITE

Description: The reaction velocity constant for the oxidation of Pu(III) by nitrite in HNO/sub 3/ solution containing ferrous sulfanate is given. The reaction rate was found to be measurable by means of spectrophotometry. The data indicate the reaction to be a pseudo first-order reaction in the region of HNO/sub 3/ and nitrite concentration of interest. The reaction velocity constant, expressed as a first-order reaction with respect to Pu, was found for several values of HNO/ sub 3/ and nitrite concentratio… more
Date: July 17, 1957
Creator: Brunstad, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prototype F-F6 demister installation at Purex for the future single-stage recovery of nitric acid from high-level wastes: Definitive design

Description: At present, the Purex Plant employs a two-stage process for the recovery of nitric acid from high-level wastes. This report summarizes the results of a design study on the Phase I installation of a prototype demister (vapor filter) between the E-F6 Concentrator and the T-F5 Acid Absorber. Further, the results of an engineering study are presented on the feasibility of the subsequent Phase II bypassing of the E-F11 Concentrator and auxiliaries to permit single-stage acid recovery, once satisfact… more
Date: July 17, 1959
Creator: Michels, L.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Sulfuric Acid-Sodium Nitrite Etch for Zircaloy-2

Description: Preliminary experiments indicate that there are no significant differences in the corrosion rates of zirconium or Zircaloy-2 after etching with the nitric--hydrofluoric solution or the sulfuric--nitrite solution, provided proper etching and washing techniques are followed. Incomplete removal of the residual etchant is deleterious to the corrosion resistance; however, this effect in the case of the sulfuric--nitrite solution is not as pronounced as in the case of the nitric--hydrofluoric acid so… more
Date: February 17, 1954
Creator: Kass, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reprocessing Uranium-Molybdenum Alloy Fuels-Dissolution in Concentrated Nitric Acid

Description: Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO/sub 3/ solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO/sub 3/. Plutonium and uranium values in washed precipitates can be recovered by… more
Date: March 17, 1960
Creator: Schulz, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Temperature on the Distribution of Nitric Acid Between Dibutyl Carbitol and Aqueous Solutions of Copper Nitrate

Description: This report follows a test made to determine the effect of temperature on the distribution of nitric acid between "carbitol" and gunk, extracting a number of samples of aqueous copper nitrate with samples of "carbitol" of various acidities. The data obtained is covered in Table 1.
Date: January 17, 1946
Creator: Shacklett, C. D. & Wilcox, W. J., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test plan for radioactive testing of a vertical direct denitration calciner

Description: A vertical calciner will be used to demonstrate the direct denitration process for converting plutonium-bearing liquors to stable plutonium rich solids. The calciner and come of its associated equipment were previously tested with non-radioactive chemicals to demonstrate operability.
Date: July 17, 1996
Creator: Fisher, F.D., Westinghouse Hanford
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactions of oxides of nitrogen (NO{sub x}) leading to the formation of nitric acid (HNO{sub 3}) in non-thermal plasmas (NTPs). White paper for the Strategic Environmental Research and Development Program (SERDP) (Compliance Project CP-1038: Development of non-thermal plasma reactor technology for control of atmospheric emissions)

Description: SERDP Compliance Project CP-1038 (Development of Non-Thermal Plasma Reactor Technology for Control of Atmospheric Emissions) has been commissioned to evaluate and develop non-thermal plasma (NTP) reactor technology, a form of low-temperature plasma chemical processing, for Department of Defense (DoD) applications. The primary emphasis is on the control of emissions of oxides of nitrogen (NO{sub x}), with a secondary emphasis on hazardous air pollutant (HAP) emission control (primarily volatile … more
Date: August 17, 1998
Creator: Rosocha, L. A.; Miziolek, A. W.; Nusca, M. J.; Chang, J. S. & Herron, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Validation of the SEPHIS Program for the Modeling of the HM Process

Description: The SEPHIS computer program is currently being used to evaluate the effect of all process variables on the criticality safety of the HM 1st Uranium Cycle process in H Canyon. The objective of its use has three main purposes. (1) To provide a better technical basis for those process variables that do not have any realistic effect on the criticality safety of the process. (2) To qualitatively study those conditions that have been previously recognized to affect the nuclear safety of the process o… more
Date: December 17, 1998
Creator: Kyser, E.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of the high-level waste high-temperature melter feed preparation flowsheet for vitrification process testing

Description: High-level waste (HLW) feed preparation flowsheet development was initiated in fiscal year (FY) 1994 to evaluate alternative flowsheets for preparing melter feed for high-temperature melter (HTM) vitrification testing. Three flowsheets were proposed that might lead to increased processing capacity relative to the Hanford Waste Vitrification Plant (HWVP) and that were flexible enough to use with other HLW melter technologies. This document describes the decision path that led to the selection of… more
Date: February 17, 1995
Creator: Seymour, R.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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