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Transuranic Decontamination Of Nitric Acid Solutions By The Truex Solvent Extraction Process
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Book Synopsis Transuranic Decontamination of Nitric Acid Solutions by the Truex Solvent Extraction Process by : George F. Vandegrift
Download or read book Transuranic Decontamination of Nitric Acid Solutions by the Truex Solvent Extraction Process written by George F. Vandegrift and published by . This book was released on 1984 with total page 116 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 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 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 503 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 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
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 Separations of f Elements by : Gregory R. Choppin
Download or read book Separations of f Elements written by Gregory R. Choppin and published by Springer Science & Business Media. This book was released on 2013-06-29 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt: The symposium which provided the incentive for this volume was conducted in San th Diego, California as a part of the 207 National Meeting of the American Chemical Society, March 13-17, 1994. It was conceived partly to continue an informal decennial sequence of sym posia dedicated to the topic off element separations. A lot has changed in the world of f ele ments over the last ten years, precipitating a change in emphasis which should be evident to most practitioners in the field. Production and reprocessing of nuclear fuels are no longer the principal drivers of f element separation technology. Separations technology for environment restoration, waste disposal, and the preparation of high purity lanthanides are now the defming parameters in this important field. These imperatives are reflected in the contributions to this volume. The symposium itself must be considered a success, as the attendance at all sessions was above expectations, despite the fact that it was conducted on the last two days of a large five day meeting. Our thanks to the speakers for their quality presentations, and to the audience who persevered to the end of a long meeting and against the temptation of the excellent weather of San Diego in the springtime. A complete list of symposium participants is given in Appendix 1. Preparation of this volume has been a relatively painless undertaking, largely as a result ofthe high quality ofthe submitted papers.
Book Synopsis Nuclear Engineering Handbook by : Kenneth D. Kok
Download or read book Nuclear Engineering Handbook written by Kenneth D. Kok and published by CRC Press. This book was released on 2016-10-03 with total page 1328 pages. Available in PDF, EPUB and Kindle. Book excerpt: Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
Book Synopsis Use of the TRUEX Process for the Pretreatment of Neutralized Cladding Removal Waste (NCRW) Sludge -- Results of FY 1990 Studies by :
Download or read book Use of the TRUEX Process for the Pretreatment of Neutralized Cladding Removal Waste (NCRW) Sludge -- Results of FY 1990 Studies written by and published by . This book was released on 1991 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt: The goal of this process is to separate the transuranic elements from the bulk components so that the bulk components can be disposed of as low-level waste with only a small transuranic-containing fraction requiring geologic disposal. The pretreatment process examined here is the one indicated to be most promising in the initial studies. It involves dissolving the unwashed sludge in nitric acid and then using the TRUEX solvent extraction process to remove the transuranic elements from the bulk components of the waste. The areas identified in this work that need additional information are gradual precipitate formation as dissolved sludge solutions age, and formation of solid material when the dissolved sludge solution is contacted with the solvent used in the TRUEX process. 5 refs., 71 figs., 10 tabs.
Book Synopsis The Chemistry of the Actinide and Transactinide Elements (3rd ed., Volumes 1-5) by : L.R. Morss
Download or read book The Chemistry of the Actinide and Transactinide Elements (3rd ed., Volumes 1-5) written by L.R. Morss and published by Springer Science & Business Media. This book was released on 2007-12-31 with total page 4059 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Chemistry of the Actinide and Transactinide Elements is a contemporary and definitive compilation of chemical properties of all of the actinide elements, especially of the technologically important elements uranium and plutonium, as well as the transactinide elements. In addition to the comprehensive treatment of the chemical properties of each element, ion, and compound from atomic number 89 (actinium) through to 109 (meitnerium), this multi-volume work has specialized and definitive chapters on electronic theory, optical and laser fluorescence spectroscopy, X-ray absorption spectroscopy, organoactinide chemistry, thermodynamics, magnetic properties, the metals, coordination chemistry, separations, and trace analysis. Several chapters deal with environmental science, safe handling, and biological interactions of the actinide elements. The Editors invited teams of authors, who are active practitioners and recognized experts in their specialty, to write each chapter and have endeavoured to provide a balanced and insightful treatment of these fascinating elements at the frontier of the periodic table. Because the field has expanded with new spectroscopic techniques and environmental focus, the work encompasses five volumes, each of which groups chapters on related topics. All chapters represent the current state of research in the chemistry of these elements and related fields.
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:
Book Synopsis TRU Decontamination of High-level Purex Waste by Solvent Extraction Using a Mixed Octyl(phenyl)-N, N-diisobutyl-carbamoylmethylphosphine Oxide by :
Download or read book TRU Decontamination of High-level Purex Waste by Solvent Extraction Using a Mixed Octyl(phenyl)-N, N-diisobutyl-carbamoylmethylphosphine Oxide written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N, N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C12-C14). The feed solution was 1.0 M in HNO3, 0.3 M in H2C2O4 and contained mixed (stable) fission products, U, Np, Pu, and Am, and a number of inert constituents, e.g., Fe and Al. The test showed that the process is capable of reducing the TRU concentration in the DSW by a factor of 4 x 104 (to
Download or read book Revue roumaine de chimie written by and published by . This book was released on 1989 with total page 708 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effect of Alpha-radiolysis on TRUEX-NPH Solvent by :
Download or read book Effect of Alpha-radiolysis on TRUEX-NPH Solvent written by and published by . This book was released on 1994 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: An unexpectedly high degradation of the TRUEX (TRansUranic EXtraction) solvent occurred during the treatment of waste solutions from the New Brunswick Laboratory. The waste solutions treated contained approximately 1 g/L of Pu-239 and 20 mg/L of Am-241. Earlier studies of [alpha]-radiolysis using carbon tetrachloride (CCl4) rather than normal paraffinic hydrocarbons (NPH) as a diluent indicated greater resistance to radiation damage than observed. For this study, the TRUEX-NPH solvent was loaded with Am-241 in nitric acid, irradiated with doses up to 3.5 Mrad, and monitored for decline in extraction capability as a function of absorbed dose. Results of this study are being used to improve the Generic TRUEX Model (GTM), a thermodynamic model that permits flowsheet design for solvent extraction processing.
Book Synopsis TRUEX Partitioning from Radioactive ICPP Sodium Bearing Waste by :
Download or read book TRUEX Partitioning from Radioactive ICPP Sodium Bearing Waste written by and published by . This book was released on 1995 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in resulting volumes of high activity waste (HAW) which must be dispositioned. Numerous studies conducted at the ICPP indicate the applicability of the TRUEX process has been demonstrated; however, these studies relied on a simulated SBW surrogate for the real waste. Consequently, a series of batch contacts were performed on samples of radioactive ICPP SBW taken from tank WM-185 to verify that actual waste would behave similarly to the simulated waste. The test results with SBW from tank WM-185 indicate the TRUEX solvent effectively extracts the actinides from the samples of actual waste. Gross alpha radioactivity, attributed predominantly to Pu and Am, was reduced from 3.14E+04 dps/mL to 1.46 dps/mL in three successive batch contacts with fresh TRUEX solvent. This reduction corresponds to a decontamination factor of DF = 20,000 or 99.995% removal of the gross a activity in the feed. The TRUEX solvent also extracted the matrix components Zr, Fe, and Hg to an appreciable extent (D{sub Zr}> 10, D{sub Fe} H"2, D{sub Hg} H"). Iron co-extracted with the actinides can be successfully scrubbed from the organic with 0.2 M HNO3. Mercury can be selectively partitioned from the actinides with either sodium carbonate or nitric acid (e"5 M HNO3) solutions.
Book Synopsis Development and Demonstration of the TRUEX Solvent Extraction Process by :
Download or read book Development and Demonstration of the TRUEX Solvent Extraction Process written by and published by . This book was released on 1993 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generic TRUEX Model (GTM) was developed for use in designing site and feed-specific TRUEX flowsheets and in estimating the space and cost requirements for installing a TRUEX process. This paper discusses data collected in support of the GTM and its use in (1) designing process flowsheets and (2) performing sensitivity analyses. Demonstration of the TRUEX process is underway at Argonne National Laboratory (ANL), where plutonium-containing analytical waste solutions generated at the DOE New Brunswick Laboratory (NBL) are being converted from TRU waste ([approximately]l g Pu/L), with no current means of disposal, to solutions that contain less than 10 nCi of transuranic elements per milliliter of waste solution. Results and implications of this demonstration are discussed in this paper.
Book Synopsis The Office of Environmental Management Technical Reports by :
Download or read book The Office of Environmental Management Technical Reports written by and published by . This book was released on 1997 with total page 972 pages. Available in PDF, EPUB and Kindle. Book excerpt:
