Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process PDF full book. Access full book title Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process by . Download full books in PDF and EPUB format.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
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
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
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
Author: Publisher: ISBN: Category : Languages : en Pages : 16
Book Description
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.
Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
The TRUEX (TRansUranium EXtraction) process is a generic actinide extraction/recovery process for the removal of all actinides from acidic nitrate and chloride nuclear waste solutions. Because of its high efficiency and flexibility and its compatibility with existing process facilities, TRUEX has now become a vital tool for the disposal of certain US defense nuclear waste. The development of TRUEX is closely coupled to the development of bifunctional extractants belonging to the carbamoylphosphoryl class and CMPO in particular. A brief review of the development of CMPO and its relationship to other bifunctional and monofunctional extractants is presented. The effect of TBP on CMPO, the selectivity of CMPO for actinides extracted from acidic nitrate media, the influence of diluents on CMPO behavior and 3rd phase formation, and the radiolysis/hydrolysis of CMPO and subsequent solvent cleanup will be highlighted. Application of TRUEX in the chemical pretreatment of specific nuclear waste streams and a summary of the current status of development and deployment of TRUEX is presented. 15 refs., 10 figs., 3 tabs.
Author: Thomas E Carleson Publisher: CRC Press ISBN: 1351357832 Category : Technology & Engineering Languages : en Pages : 503
Book Description
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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The TRUEX (TRansUranic EXtraction) solvent extraction process has the ability to remove, separate, and recover transuranic (TRU) elements from acidic nuclear waste solutions. A computer model of the TRUEX process is currently being developed for use in flowsheet design and process optimization. The correlations that are to be used in the model for generating extraction distribution ratios are based on chemical mass action principles and require calculation of aqueous and organic phase speciation. Aqueous phase activity coefficients are calculated using methods available in the literature, while the organic phase species are treated in terms of ideal associated solution theory. This approach is demonstrated for the extraction of HNO3, HTcO4, and americium nitrate by n-octyl(phenyl)-N, N-diisobutylcarbamoyl-methylphosphine oxide (CMPO)--the primary metal extractant in the TRUEX solvent. 23 refs., 5 figs.
Author: Publisher: ISBN: Category : Languages : en Pages : 79
Book Description
In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.
Author: Publisher: ISBN: Category : Languages : en Pages : 79
Book Description
In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.
Author: Vladimir S Kislik Publisher: Elsevier ISBN: 0444537791 Category : Technology & Engineering Languages : en Pages : 573
Book Description
The main challenge in modern solvent extraction separation is that most techniques are mainly empirical, specific and particular for narrow fields of practice and require a large degree of experimentation. This concise and modern book provides a complete overview of both solvent extraction separation techniques and the novel and unified competitive complexation/solvation theory. This novel and unified technique presented in the book provides a key for a preliminary quantitative prediction of suitable extraction systems without experimentation, thus saving researchers time and resources. Analyzes and compares both classical and new competitive models and techniques Offers a novel and unified competitive complexation / solvation theory that permits researchers to standardize some parameters, which decreases the need for experimentation at R&D Presents examples of applications in multiple disciplines such as chemical, biochemical, radiochemical, pharmaceutical and analytical separation Written by an outstanding scientist who is prolific in the field of separation science
Author: Publisher: ISBN: Category : Languages : en Pages : 0
Book Description
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.
Author: 
Author: 
Author: 
Author: 
Author: Thomas E Carleson
Author: 
Author: 
Author: 
Author: Vladimir S Kislik
Author: 
Author: