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Solvent Composition Impacts on the Extraction of Uranium and Plutonium in the Caustic Side Solvent Extraction Process

Solvent Composition Impacts on the Extraction of Uranium and Plutonium in the Caustic Side Solvent Extraction Process PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The potential for criticality in the proposed Salt Waste Processing Facility is low but must be addressed in support of Authorization Basis development. This report describes tests and calculations to assess the issues and fulfills the requested information.

Solvent Composition Impacts on the Extraction of Uranium and Plutonium in the Caustic Side Solvent Extraction Process

Solvent Composition Impacts on the Extraction of Uranium and Plutonium in the Caustic Side Solvent Extraction Process PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The potential for criticality in the proposed Salt Waste Processing Facility is low but must be addressed in support of Authorization Basis development. This report describes tests and calculations to assess the issues and fulfills the requested information.

La turuleta

La turuleta PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Solvent Extraction of Uranium

Solvent Extraction of Uranium PDF Author:
Publisher:
ISBN:
Category : Solvent extraction
Languages : en
Pages : 24

Book Description


Caustic-Side Solvent Extraction Solvent-Composition Recommendation

Caustic-Side Solvent Extraction Solvent-Composition Recommendation PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

Book Description
The U.S. Department of Energy has selected caustic-side solvent extraction as the preferred cesium removal technology for the treatment of high-level waste stored at the Savannah River Site. Data for the solubility of the extractant, calix[4]arene-bis(tert-octyl benzo-crown-6), acquired and reported for the Salt Processing Program down-select decision, showed the original solvent composition to be supersaturated with respect to the extractant. Although solvent samples have been observed for approximately 1 year without any solids formation, work was completed to define a new solvent composition that was thermodynamically stable with respect to solids formation and to expand the operating temperature with respect to third-phase formation. Chemical and physical data as a function of solvent component concentrations were collected. The data included calix[4]arene-bis(tert-octyl benzo-crown-6) solubility; cesium distribution ratio under extraction, scrub, and strip conditions; flow sheet robustness; temperature range of third-phase formation; dispersion numbers for the solvent against waste simulant, scrub and strip acids, and sodium hydroxide wash solutions; solvent density; viscosity; and surface and interfacial tension. These data were mapped against a set of predefined performance criteria. The composition of 0.007 M calix[4]arene-bis(tert-octyl benzo-crown-6), 0.75 M 1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol, and 0.003 M tri-n-octylamine in the diluent Isopar{reg_sign} L provided the best match between the measured properties and the performance criteria. Therefore, it is recommended as the new baseline solvent composition.

The Purex Process

The Purex Process PDF Author: E. R. Irish
Publisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72

Book Description


Recovery of By-product Uranium by the Solvent Extraction Method

Recovery of By-product Uranium by the Solvent Extraction Method PDF Author: R. E. Berning
Publisher:
ISBN:
Category : Phosphoric acid
Languages : en
Pages : 134

Book Description
A solvent extraction process for the recovery of Uranium from Phosphoric Acid is described. The process steps which include reduction, extraction, unloading and acid clean-up are presented in detail. An estimated process cost is also presented.

Caustic-Side Solvent Extraction

Caustic-Side Solvent Extraction PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
This work was undertaken to optimize the solvent used in the Caustic Side Solvent Extraction (CSSX) process and to measure key chemical and physical properties related to its performance in the removal of cesium from the alkaline high-level salt waste stored in tanks at the Savannah River Site. The need to adjust the solvent composition arose from the prior discovery that the previous baseline solvent was supersaturated with respect to the calixarene extractant. The following solvent-component concentrations in Isopar{reg_sign} L diluent are recommended: 0.007 M calix[4]arene-bis(tert-octylbenzo-crown-6) (BOBCalixC6) extractant, 0.75 M 1-(2,2,3,3-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol (Cs-7SB) phase modifier, and 0.003 M tri-n-octylamine (TOA) stripping aid. Criteria for this selection included BOBCalixC6 solubility, batch cesium distribution ratios (D{sub Cs}), calculated flowsheet robustness, third-phase formation, coalescence rate (dispersion numbers), and solvent density. Although minor compromises within acceptable limits were made in flowsheet robustness and solvent density, significant benefits were gained in lower risk of third-phase formation and lower solvent cost. Data are also reported for the optimized solvent regarding the temperature dependence of D{sub Cs} in extraction, scrubbing, and stripping (ESS); ESS performance on recycle; partitioning of BOBCalixC6, Cs-7SB, and TOA to aqueous process solutions; partitioning of organic anions; distribution of metals; solvent phase separation at low temperatures; solvent stability to elevated temperatures; and solvent density and viscosity. Overall, the technical risk of the CSSX process has been reduced by resolving previously identified issues and raising no new issues.

Extraction of Uranium, Neptunium and Plutonium from Caustic Media

Extraction of Uranium, Neptunium and Plutonium from Caustic Media PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
5 Fundamental research on uranium, neptunium and plutonium separation from alkaline media using solvent extraction is being conducted. Specific extractants for these actinides from alkaline media have been synthesized to investigate the feasibility of selective removal of these elements. Two families of extractants have been studied: terephthalamide and tetra(hydroxybenzyl)ethylene diamine derivatives. Fundamental studies were conducted to characterize their extraction behavior from a wide variety of aqueous conditions. The terephthalamide derivatives exhibit a significant extraction strength along with a discriminatory behavior among the actinides, plutonium being extracted the most strongly. Quantitative extraction of plutonium and moderate extraction of neptunium and uranium was achieved from a simple caustic solution. Interestingly, strontium is also quantitatively extracted by these derivatives. However, their stability to highly caustic solutions still needs to be imp roved. Tetra(hydroxybenzyl)ethylene diamine derivatives exhibit a very good stability to caustic conditions and are currently being studied.

Hydroxylamine Nitrate Reduction of Plutonium (IV)

Hydroxylamine Nitrate Reduction of Plutonium (IV) PDF Author: G. Scott Barney
Publisher:
ISBN:
Category : Hydroxylamine
Languages : en
Pages : 24

Book Description


Solvent Extraction of Uranium from Carbonate Solutions

Solvent Extraction of Uranium from Carbonate Solutions PDF Author: F. G. Seeley
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 48

Book Description