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The Truex Process For Recovery Of Plutonium And Americium From Nitric Acid Waste Solution
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Book Synopsis The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies by : R. A. Leonard
Download or read book The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies written by R. A. Leonard and published by . This book was released on 1985 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies by :
Download or read book Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX process solvent in these experiments was a solution of TBP and octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) dissolved in carbon tetrachloride. A flowsheet was designed on the basis of measured batch distribution ratios to reduce the TRU content of the solidified raffinate to less than or equal to 10 nCi/g and was tested in a countercurrent experiment performed in a 14-stage Argonne-model centrifugal contractor. The process solvent was recycled without cleanup. An unexpectedly high evaporative loss of CCl4 resulted in concentration of the active extractant, CMPO, to nearly 0.30M in the solvent. Results are consistent with this higher CMPO concentration. The raffinate contained only 2 nCi/g of TRU, but the higher CMPO concentration resulted in reduced effectiveness in the stripping of americium from the solvent. Conditions can be easily adjusted to give high yields and good separation of americium and plutonium. Experimental studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CCl4 showed that solvent degradation would be (1) minimal for a year of processing this typical feed, which contained no fission products, and (2) could be explained almost entirely by hydrolytic and radiolytic damage to TBP. Even for gross amounts of solvent damage, scrubbing with aqueous sodium carbonate solution restored the original americium extraction and stripping capability of the solvent. 43 refs., 5 figs., 36 tabs.
Book Synopsis The Truex Process for Recovery of Plutonium and Americium from Nitric Acid Waste Solution by : R. A. Leonard
Download or read book The Truex Process for Recovery of Plutonium and Americium from Nitric Acid Waste Solution written by R. A. Leonard and published by . This book was released on 1987 with total page 115 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The TRUEX process for recovery of plutonium and americium from nitric acid waste solutions : continuing development studies, FY 1986 by : R. A. Leonard
Download or read book The TRUEX process for recovery of plutonium and americium from nitric acid waste solutions : continuing development studies, FY 1986 written by R. A. Leonard and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process by :
Download or read book Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-level liquid waste is produced during the processing of irradiated nuclear fuel by the PUREX process. In some cases the treatment of metallurgical scrap to recover the plutonium values also generates a nitric acid waste solution. Both waste solutions contain sufficient concentrations of transuranic elements (mostly 241Am) to require handling and disposal as a TRU waste. This paper describes a recently developed solvent extraction/recovery process called TRUEX (transuranium extraction) which is designed to reduce the TRU concentration in nitric waste solutions to
Book Synopsis Secondary Recovery of Plutonium and Americium from Process Waste Streams by Solvent Extraction by :
Download or read book Secondary Recovery of Plutonium and Americium from Process Waste Streams by Solvent Extraction written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A solvent extraction process is being evaluated for the secondary recovery of plutonium and americium from Rocky Flats waste streams. The bidentate organophosphorus compounds dihexyl-N, N-diethylcarbamylmethylene phosphonate and its dibutyl analogue have been shown to be selective extractants for the actinides from solutions of nitric acid. The results from laboratory test runs in which the organophosphorus extractants were used for processing secondary waste solutions will be presented. Solvent extractant properties and purification procedures are discussed.
Book Synopsis TRUEX Processing of Plutonium Analytical Solutions at Argonne National Laboratory by :
Download or read book TRUEX Processing of Plutonium Analytical Solutions at Argonne National Laboratory written by and published by . This book was released on 1995 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt: The TRUEX (TRansUranic EXtraction) solvent extraction process was developed at Argonne National Laboratory (ANL) for the Department of Energy. A TRUEX demonstration completed at ANL involved the processing of analytical and experimental waste generated there and at the New Brunswick Laboratory. A 20-stage centrifugal contactor was used to recover plutonium, americium, and uranium from the waste. Approximately 84 g of plutonium, 18 g of uranium, and 0.2 g of americium were recovered from about 118 liters of solution during four process runs. Alpha decontamination factors as high as 65,000 were attained, which was especially important because it allowed the disposal of the process raffinate as a low-level waste. The recovered plutonium and uranium were converted to oxide; the recovered americium solution was concentrated by evaporation to approximately 100 ml. The flowsheet and operational procedures were modified to overcome process difficulties. These difficulties included the presence of complexants in the feed, solvent degradation, plutonium precipitation, and inadequate decontamination factors during startup. This paper will discuss details of the experimental effort.
Book Synopsis Recovery of Plutonium from Incinerator Ash by : F. E. Butler
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:
Book Synopsis New Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications by : L. Cécille
Download or read book New Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications written by L. Cécille and published by Springer. This book was released on 1991-07-11 with total page 332 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Proceedings of a technical seminar jointly organized by the Commission of the European Communities (CEC), Directorate-General for Science, Research, and Development and by the Italian Commission for Nuclear and Alternative Energy Sources (ENEA)"--T.p. verso.
Book Synopsis Separation Techniques in Nuclear Waste Management (1995) by : Thomas E Carleson
Download or read book Separation Techniques in Nuclear Waste Management (1995) written by Thomas E Carleson and published by CRC Press. This book was released on 2017-11-22 with total page 334 pages. Available in PDF, EPUB and Kindle. Book excerpt: Separation Techniques in Nuclear Waste Management is an up-to-date, comprehensive survey of processes for separation of nuclear wastes. Comprised of articles by scientists and engineers at universities and national laboratories in the U.S. and overseas, the book provides excellent reference information for individuals working in nuclear waste management. Specifically, the book covers current separation technologies and techniques for waste liquid, solid, and gas streams that contain radionuclides. Such wastes are typical of those produced as a result of nuclear materials processing and spent fuel reprocessing. Chapters on promising new technologies and state-of-the-art processes currently in use provide valuable information for design engineers, as well as for research scientists. The articles in Separation Techniques in Nuclear Waste Management are brief and concise - designed for quick access to pertinent information. Many of the contributors are leaders in their fields. It is the most current survey available of the latest nuclear waste management techniques.
Book Synopsis Recovery of Plutonium from Nitric Acid Waste by : A. C. Muscatello
Download or read book Recovery of Plutonium from Nitric Acid Waste written by A. C. Muscatello and published by . This book was released on 1986 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Purex Process written by E. R. Irish and published by . This book was released on 1957 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Recovery of Plutonium and Americium from Chloride Salt Wastes by Solvent Extraction by :
Download or read book Recovery of Plutonium and Americium from Chloride Salt Wastes by Solvent Extraction written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Plutonium and americium can be recovered from aqueous waste solutions containing a mixture of HCl and chloride salt wastes by the coupling of two solvent extraction systems: tributyl phosphate (TBP) in tetrachloroethylene (TCE) and octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in TCE. In the flowsheet developed, the salt wastes are dissolved in HCl, the Pu(III) is oxidized to the IV state with NaClO2 and recovered in the TBP-TCE cycle, and the Am is then removed from the resultant raffinate by the CMPO-TCE cycle. The consequences of the feed solution composition and extraction behavior of these species on the process flowsheet design, the Pu-product purity, and the decontamination of the aqueous raffinate from transuranic elements are discussed. 16 refs., 6 figs.
Book Synopsis Recovery of Plutonium from Irradiated Plutonium-aluminum Alloy by :
Download or read book Recovery of Plutonium from Irradiated Plutonium-aluminum Alloy written by and published by . This book was released on 1962 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis New Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications by : Messrs L. Cecille
Download or read book New Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications written by Messrs L. Cecille and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 363 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this technical seminar was to evaluate the present state of the art in matter of advanced separation techniques like solvent extraction, ion-exchange, chemical precipitation, membrane and electrical processes for the treatment of radioactive liquid waste and a selection of some specific industrial non-radioactive effluents. Through this initiative, the organisers aimed at promoting the exchange of information between scientists from various origins (universities, research centres and industries) while contributing to the necessary overcoming of the artificial barriers which too often limit the "technology transfer" between the nuclear and non-nuclear sectors. Vll CONTENTS PREFACE ........................................ V ABBREVIATIONS ...................................... xiv OPENING SESSION WELCOME ADDRESS C. MANCINI (ENEA) .................................... 3 OPENING ADDRESS S. FINZI (CEC) ....................................... 7 AREAS WHERE ADVANCED SEPARATION TECHNIQUES ARE DESIRABLE G. GROSSI (ENEA), L. CECILLE (CEC) ....................... 11 REVIEW OF NEW EXTRACT ANTS POTENTIALLY APPLICABLE TO THE PROCESSING OF RADIOACTIVE LIQUID WASTES (Summary) P.R. DANESI, International Atomic Energy Agency, Vienna, Austria . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 . . . . . . . . . .
Book Synopsis Actinide Removal from Nitric Acid Waste Streams by :
Download or read book Actinide Removal from Nitric Acid Waste Streams written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Actinide separations research at the Rocky Flats Plant (RFP) has found ways to significantly improve plutonium secondary recovery and americium removal from nitric acid waste streams generated by plutonium purification operations. Capacity and breakthrough studies show anion exchange with Dowex 1x4 (50 to 100 mesh) to be superior for secondary recovery of plutonium. Extraction chromatography with TOPO(tri-n-octyl-phosphine oxide) on XAD-4 removes the final traces of plutonium, including hydrolytic polymer. Partial neutralization and solid supported liquid membrane transfer removes americium for sorption on discardable inorganic ion exchangers, potentially allowing for non-TRU waste disposal.
Book Synopsis Nuclear Wastes by : National Research Council
Download or read book Nuclear Wastes written by National Research Council and published by National Academies Press. This book was released on 1996-02-23 with total page 590 pages. Available in PDF, EPUB and Kindle. Book excerpt: Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
