Author: N. SrinivasanPublisher:
ISBN:
Category :
Languages : en
Pages : 27
Book Description
Co-extraction Studies of Uranium and Plutonium with Tributyl Phosphate in Nitric Acid Media
Author: N. SrinivasanThe Tributyl Phosphate-nitric Acid Complex and Its Role in Uranium Extraction
Author: Thomas J. CollopyPublisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 24
Book Description
Some Factors Influencing the Use of Tributyl Phosphate for the Extraction of Uranium in Analysis
Author: T. W. BartlettPublisher:
ISBN:
Category : Chemistry
Languages : en
Pages : 28
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. LeonardLaboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel
Author: J. H. GoodePublisher:
ISBN:
Category : Extraction (Chemistry)
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.
Solvent Extraction Data for Plutonium
Author: Linda Lou SmithPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 276
Book Description
Recovery of Irradiated Uranium by a Two-stage Differential Extraction Procedure
Author: R. E. McHenryPublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 42
Book Description
The Purex Process
Author: E. R. IrishPublisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72
Book Description
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