Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Extraction of Plutonium by Hexone from Aqueous Solutions Containing Nitric Acid
Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Extraction of plutonium by hexone from aqueous solutions containing nitric acid
Author: D. R. MackenziePlutonium Extraction from Nitrate and Sulfate Solutions by Amines and Organophosphorus Compounds
Author: D. E. HornerPublisher:
ISBN:
Category : Nuclear reactions
Languages : en
Pages : 70
Book Description
Solvent Extraction Data for Plutonium
Author: Linda Lou SmithPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 276
Book Description
Thermochemical Measurements of Purex Process Solutions
Author: Glenn A. BurneyPublisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
The Extraction Mechanism of Plutonium (IV) TTA Chelate in Sec-butylbenzene-nitric Acid-uranyl Nitrate Mixtures
Author: D. L. HeisigPublisher:
ISBN:
Category : Nitric acid
Languages : en
Pages : 76
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.
Analytical Chemistry of Plutonium
Author: Institut geokhimii i analiticheskoĭ khimii im. V.I. VernadskogoPublisher: Butterworth-Heinemann
ISBN:
Category : Science
Languages : en
Pages : 460
Book Description
Solvent extraction study of tracer plutonium and hafnium in the...
Author: Mohamed Kamal Kamel ShehataPublisher:
ISBN:
Category :
Languages : en
Pages : 156
Book Description