Author: Zdenek KolarikPublisher:
ISBN:
Category :
Languages : de
Pages : 18
Book Description
Solvent Extraction Recovery of Plutonium from Raffinate Concentrates in the Purex Process
Author: Zdenek KolarikThe Purex Process
Author: E. R. IrishPublisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72
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. LeonardPerformance of a Plutonium Reflux Solvent Extraction System
Author: B. F. JudsonPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 30
Book Description
Extraction 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.
DI-2-Amyl 2-Butylphosphonate as an Extractant for the Recovery of Uranium and Plutonium
Author: Thomas H. SiddallPublisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
Recovery of Plutonium from Irradiated Plutonium-aluminum Alloy
Author: Description of Purex Plant Process
Author: E. R. IrishPublisher:
ISBN:
Category : Fission products
Languages : en
Pages : 18
Book Description
The Purex process is a continuous solvent extraction process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
D2EHPA Extraction Recovery of Neptunium and Plutonium from Purex Acid Sludge Solutions
Author: W. W. SchulzPublisher:
ISBN:
Category : Neptunium
Languages : en
Pages : 52
Book Description
Author: