Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies 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 Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies PDF full book. Access full book title Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies by . Download full books in PDF and EPUB format.

Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies

Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies PDF 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.

Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies

Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies PDF 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 Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies

The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies PDF Author: R. A. Leonard
Publisher:
ISBN:
Category :
Languages : en
Pages : 88

Book Description


The TRUEX process for recovery of plutonium and americium from nitric acid waste solutions : continuing development studies, FY 1986

The TRUEX process for recovery of plutonium and americium from nitric acid waste solutions : continuing development studies, FY 1986 PDF Author: R. A. Leonard
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


The Truex Process for Recovery of Plutonium and Americium from Nitric Acid Waste Solution

The Truex Process for Recovery of Plutonium and Americium from Nitric Acid Waste Solution PDF Author: R. A. Leonard
Publisher:
ISBN:
Category : Americium
Languages : en
Pages : 115

Book Description


Separation Techniques in Nuclear Waste Management (1995)

Separation Techniques in Nuclear Waste Management (1995) PDF Author: Thomas E Carleson
Publisher: 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.

Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process

Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process PDF 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

Secondary Recovery of Plutonium and Americium from Process Waste Streams by Solvent Extraction PDF 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.

Ion Exchange and Solvent Extraction

Ion Exchange and Solvent Extraction PDF Author: Bruce A. Moyer
Publisher: CRC Press
ISBN: 142005970X
Category : Science
Languages : en
Pages : 682

Book Description
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

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1032

Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 676

Book Description