Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
The Extraction And Recovery Of Plutonium And Americium From Nitric Acid Waste Solutions By The Truex Process Continuing Development Studies
Download The Extraction And Recovery Of Plutonium And Americium From Nitric Acid Waste Solutions By The Truex Process Continuing Development Studies full books in PDF, epub, and Kindle. Read online The Extraction And Recovery Of Plutonium And Americium From Nitric Acid Waste Solutions By The Truex Process Continuing Development Studies ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
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 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 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 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 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 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 Ion Exchange and Solvent Extraction by : Bruce A. Moyer
Download or read book Ion Exchange and Solvent Extraction written by Bruce A. Moyer and published by CRC Press. This book was released on 2009-08-19 with total page 682 pages. Available in PDF, EPUB and Kindle. Book excerpt: The growth in the world's nuclear industry, motivated by peaking world oil supplies, concerns about the greenhouse effect, and domestic needs for energy independence, has resulted in a heightened focus on the need for next-generation nuclear fuel-cycle technologies. Ion Exchange and Solvent Extraction: A Series of Advances, Volume 19 provides a com
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 1652 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1985 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 630 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Transuranic Decontamination of Nitric Acid Solutions by the TRUEX Solvent Extraction Process by :
Download or read book Transuranic Decontamination of Nitric Acid Solutions by the TRUEX Solvent Extraction Process written by and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 solvent (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste. Assessments were made of the use of two TRUEX solvents: one incorporating the well-studied dihexyl-N, N-diethylcarbamoylmethylphosphonate (DHDECMP) and a second incorporating an extractant with superior properties for a 1M HNO3 acid feed, octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (O/sub phi/D(IB)CMPO). In this report, conceptual flowsheets for the removal of soluble TRUs from high-level nuclear wastes using these two TRUEX proces solvents are presented, and flowsheet features are discussed in detail. The conceptual flowsheet for TRU-element removal from a PUREX waste by the O/sub phi/D(IB)CMPO-TRUEX process solvent was tested in a bench-scale countercurrent experiment, and results of that experiment are presented and discussed. The conclusion of this study is that the TRUEX process is able to separate TRUs from high-level wastes so that the major portion of the solid waste (approx. 99%) can be classified as non-TRU. Areas where more experimentation is needed are listed at the end of the report. 45 references, 17 figures, 56 tables.
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 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.
Download or read book Technical Reports Series written by and published by . This book was released on 1994 with total page 1362 pages. Available in PDF, EPUB and Kindle. Book excerpt:
