Download or read book Recovery of Plutonium from Incinerator Ash written by F. E. Butler and published by . This book was released on 1964 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Plutonium Recovery from Incinerator Ash and Centrifuge Sludge by Peroxide Fusion written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Small scale Study on the Dissolution and Anion exchange Recovery of Plutonium from Rocky Flats Plant Incinerator Ash written by Thomas W. Blum and published by . This book was released on 1990 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fluorination of Incinerator Ash by Hydrofluorination Or Ammonium Bifluoride Fusion for Plutonium Recovery written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Incinerator ash containing small quantities of plutonium has been accumulating across the defense complex for many years. Although the total Pu inventory is small, the ash is a nondiscardable residue which presents storage and accountability difficulties. The work discussed here is the result of a joint exploratory effort between members of Savannah River Laboratory and Los Alamos National Laboratory to compare two proposed pyrochemical pretreatments of incinerator ash prior to aqueous processing. These experiments attempted to determine the relative effectiveness of hydrofluorination and ammonium bifluoride fusion as head-end operations for a two step aqueous recovery method. The two pretreatments are being considered as possible second generation enhancements for the New Special Recovery Facility nearing operation at Savannah River Plant. Experimental results and potential engineering concerns are discussed. 3 figs.
Download or read book Plutonium Waste Incineration Using Pyrohydrolysis written by and published by . This book was released on 1991 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Waste generated by Savannah River Site (SRS) plutonium operations includes a contaminated organic waste stream. A conventional method for disposing of the organic waste stream and recovering the nuclear material is by incineration. When the organic material is burned, the plutonium remains in the incinerator ash. Plutonium recovery from incinerator ash is highly dependent on the maximum temperature to which the oxide is exposed. Recovery via acid leaching is reduced for a high fired ash (>800°C), while plutonium oxides fired at lower decomposition temperatures (400--800°C) are more soluble at any given acid concentration. To determine the feasibility of using a lower temperature process, tests were conducted using an electrically heated, controlled-air incinerator. Nine nonradioactive, solid, waste materials were batch-fed and processed in a top-heated cylindrical furnace. Waste material processing was completed using a 19-liter batch over a nominal 8-hour cycle. A processing cycle consisted of 1 hour for heating, 4 hours for reacting, and 3 hours for chamber cooling. The water gas shift reaction was used to hydrolyze waste materials in an atmosphere of 336% steam and 4.4% oxygen. Throughput ranged from 0.14 to 0.27 kg/hr depending on the variability in the waste material composition and density.
Download or read book Incineration and Incinerator Ash Processing written by and published by . This book was released on 1991 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Parallel small-scale studies on the dissolution and anion exchange recovery of plutonium from Rocky Flats Plant incinerator ash were conducted at the Los Alamos National Laboratory and at the Rocky Flats Plant. Results from these two studies are discussed in context with incinerator design considerations that might help to mitigate ash processing related problems. 11 refs., 1 fig., 1 tab.
Download or read book EVALUATION OF METHODS TO RECOVER PLUTONIUM FROM INCINERATOR ASH written by and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Plutonium Residue Recovery PuRR Project Quarterly Progress Report April June 1989 written by and published by . This book was released on 1989 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: A material-balance flowsheet for ash-heel processing has been prepared. The major process features are (1) reduction of Pu into a calcium-zinc alloy and selective electrolytic recovery of the Pu from the alloy, (2) removal of americium as a waste, (3) concentration of nontransuranic tramp elements in a zinc waste, (4) removal of oxygen and recovery of calcium by electrolysis of CaO, and (5) zinc recycle by evaporation. Based on this idealized flowsheet, the mass of solid waste is only 62% of that of the original residue. This is accomplished by recycling virtually all the reagents and discarding the oxygen as CO and CO2. The pyrochemical recovery of Pu from incinerator ash heel from the Rocky Flats Plant was investigated. During this period, zinc-calcium alloys were used to reduce the PuC2 in the ash. Reduction of ash heel has been attempted with zinc-calcium alloys containing 2, 6, and 10 wt% calcium after the reduction. These resulted in extractions of 95%, 97%, and 99.5%, respectively, of the Pu from the salt. Following exposure of the reduction alloy to a ZnCl2-bearing salt, the Pu was removed effectively from the alloy; however, the Pu recovered in the salt did not complete the material balance. Experiments were made to test a calcium-zinc reference electrode against a Zn-Ca-Mg-Al liquid alloy. The results agreed well with calculated potentials, and such electrodes are promising for application to process monitoring. Calculations were made that verify that most of the americium in the molten salt is present in the divalent state when distributed between liquid Pu and NaCl-KCl. The AmCl2 activity coefficient is about 10 times that of PuCl3 in the salt mixture.
Download or read book Recovery of Plutonium from Refractory Residues Using a Sodium Peroxide Pretreatment Process written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The recycle of plutonium from refractory residues is a necessary activity for the nuclear weapon production complex. Traditionally, high-fired plutonium oxide (PuO2) was leached from the residue matrix using a nitric acid/fluoride dissolving flowsheet. The recovery operations were time consuming and often required multiple contacts with fresh dissolving solution to reduce the plutonium concentration to levels where residual solids could be discarded. Due to these drawbacks, the development of an efficient process for the recovery of plutonium from refractory materials is desirable. To address this need, a pretreatment process was developed. The development program utilized a series of small-scale experiments to optimize processing conditions for the fusion process and demonstrate the plutonium recovery efficiency using ceramic materials developed as potential long-term storage forms for PuO2 and an incinerator ash from the Rocky Flats Environmental Technology Site (Rocky Flats) as te st materials.
Download or read book Nuclear Materials written by United States. General Accounting Office and published by . This book was released on 1992 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Waste Management Analysis for the Nuclear Fuel Cycle written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Evaluation of the Ce(IV)-NHO3 system for recovery of actinides from incinerator ash is continuing. High-fired americium-traced plutonium oxide was completely solubilized in this system and recovery of actinides from incinerator ash was greater than or equal to 95%. Recovery of solubilized plutonium was done by solvent extraction using tributyl phosphate. Tervalent actinides will be recovered by a bidentate organophosphorus solvent extractant. The Ce(IV)-HNO3 system was compared with the F−-HNO3 system now in common use. Advantages of the former include less equipment corrosion, no volatilization of silica, and better recovery of actinide in the initial contact. However, additional contacts do not significantly improve recovery (because silica is not solubilized), and the system requires a large liquid/solid ratio for efficient actinide recovery.
Download or read book Development of a Plutonium 239 Recovery Incinerator written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A Plutonium-239 Recovery Incinerator is being developed for the Savannah River Plant (SRP) to reduce the volume of solid glovebox waste and to allow recovery of Pu-239 from the waste. The process will also allow treatment of some waste materials that are not certifiable for disposal at the Waste Isolation Pilot Plant (WIPP). It will consist of two electrically heated combustion chambers (furnace and afterburner) and a dry filtration off-gas system. A unique feature of the process is that it uses pyrohydrolysis to produce an ash that is amenable to Pu recovery through nitric acid/HF dissolution. A series of thermogravimetric (TGA) analyses have been performed to characterize potential incinerator feed materials. A functioning furnace mockup was built and operated to demonstrate electrically-heated pyrohydrolysis operation. 8 refs., 4 figs.
Download or read book CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE D D OF THE 232 Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT PFP written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place.
Download or read book Nuclear Science and Technology written by D.C. Bamber and published by European Communities. This book was released on 1984-12-01 with total page 173 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Management of Plutonium Contaminated Waste written by G. Birkhoff and published by CRC Press. This book was released on 1981 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Plutonium Leachability from Alternative Transuranic Incinerator Ash Waste Forms written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Leaching experiments were conducted to determine the rate of plutonium release from Portland cement, urea-formaldehyde, and polyester-styrene waste forms incorporating incinerator ash waste. A modified IAEA leach test procedure was employing using demineralized water, simulated WIPP Brine B, simplified sodium dominated groundwater, simplified calcium dominated groundwater and simplified bicarbonate dominated groundwater leachants. The data obtained provided a good fit to a diffusion release model for semi-infinite media. This model allows the calculation of effective diffusivities for plutonium release and provides a means for the prediction of long-term plutonium releases from full-scale waste forms. The effective diffusivities determined for Portland cement and polyester-styrene waste forms varied from 1.6 x 10−22 to 3.9 x 10−2° cm2/sec. Plutonium release was more rapid from urea-formaldehyde waste forms which exhibited effective diffusivities of 2.3 x 10−18 to 1.1 x 10−14 cm2/sec. The lowest release rates were obtained for leaching in WIPP Brine B. Effective diffusivities in the range of 10−22 to 10−2° cm2/sec result in predicted fraction plutonium releases of 1.9 x 10−6 to 1.9 x 10−5 in 105 years (neglecting decay) from 210 liter (55 gallon drum) waste forms. As a result of the low effective diffusivities determined and for the long half-lives of TRU radionuclides, waste form stability may be the primary determinant of activity release over the time period that must be considered for TRU waste disposal.
Download or read book Management of Plutonium Contaminated Waste written by G. Birkhoff and published by CRC Press. This book was released on 1981 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:
