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Uranium Partition Between Tri-n-butyl Phosphate and Aqueous Uranyl Nitrate Solutions

Author: T. J. Collopy
Publisher:
ISBN:
Category : Hydrometallurgy
Languages : en
Pages : 30

Book Description

Uranium Partition Between Tri-n-butyl Phosphate and Aqueous Uranyl Nitrate Solutions

Author: T. J. Collopy
Publisher:
ISBN:
Category : Hydrometallurgy
Languages : en
Pages : 30

Book Description

The Tributyl Phosphate-nitric Acid Complex and Its Role in Uranium Extraction

Author: Thomas J. Collopy
Publisher:
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. Bartlett
Publisher:
ISBN:
Category : Chemistry
Languages : en
Pages : 28

Book Description

Comparison of Tributyl Phosphate and Dibutoxytetraethyleneglycol as Extractants of Uranium

Author: William Blythe Wright
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 20

Book Description

Role of Hydroxide Ion During Stripping of Uranium from Tri-n-butyl Phosphate

Author: T. J. Collopy
Publisher:
ISBN:
Category : Hydrometallurgy
Languages : en
Pages : 42

Book Description

The Recovery of Uranium from Sulfate Solutions by Solvent Extraction with Tributyl Phosphate

Author: J. R. Flanary
Publisher:
ISBN:
Category : Nuclear reactions
Languages : en
Pages : 20

Book Description

Self-diffusion of Uranyl Ion and the Uranium Tributyl Phosphate Complex

Author: H. T. Hahn
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 44

Book Description

Calculated Equilibrium Distributions for the Uranyl Nitrate-tributyl Phosphate-dilute Nitric Acid System for Temperatures Between 25 and 75 C

Author: N. P. Wilburn
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 70

Book Description

Method for Photochemical Reduction of Uranyl Nitrate by Tri-N-butyl Phosphate and Application of this Method to Nuclear Fuel Reprocessing

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Uranyl ion in solution in tri-n-butyl phosphate is readily photochemically reduced to U(IV). The product U(IV) may effectively be used in the Purex process for treating spent nuclear fuels to reduce Pu(IV) to Pu(III). The Pu(III) is readily separated from uranium in solution in the tri-n-butyl phosphate by an aqueous strip.

Tributyl Phosphate Extraction of Uranium from Ammonium Nitrate Solutions

Author: R. A. Kent
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 18

Book Description