Author: R. A. LeonardPublisher:
ISBN:
Category :
Languages : en
Pages : 88
Book Description
The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies
Author: R. A. LeonardExtraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
The Truex Process for Recovery of Plutonium and Americium from Nitric Acid Waste Solution
Author: R. A. LeonardPublisher:
ISBN:
Category : Americium
Languages : en
Pages : 115
Book Description
The TRUEX process for recovery of plutonium and americium from nitric acid waste solutions : continuing development studies, FY 1986
Author: R. A. LeonardSolvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process
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
Secondary Recovery of Plutonium and Americium from Process Waste Streams by Solvent Extraction
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
TRUEX Processing of Plutonium Analytical Solutions at Argonne National Laboratory
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 29
Book Description
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.
Recovery of Plutonium from Incinerator Ash
Author: F. E. ButlerNew Separation Chemistry Techniques for Radioactive Waste and Other Specific Applications
Author: L. CécillePublisher: Springer
ISBN:
Category : Juvenile Nonfiction
Languages : en
Pages : 332
Book Description
"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.
Separation Techniques in Nuclear Waste Management (1995)
Author: Thomas E CarlesonPublisher: CRC Press
ISBN: 1351357840
Category : Technology & Engineering
Languages : en
Pages : 334
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.