Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.).
Purex Process for Plutonium and Uranium Recovery
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.).
The Purex Process
Author: E. R. Irish
Publisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72
Book Description
Publisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72
Book Description
Modified Purex Process for the Separation and Recovery of Plutonium--uranium Residues
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A modified (one-cycle) Purex process has been developed for the separation and recovery of plutonium and uranium from mixed actinide residues. The process utilizes 30 vol % tributyl phosphate--dodecane to extract uranium from a 5M nitric acid-plutonium (III)-uranium(VI) feed. After uranium extraction, plutonium in the aqueous feed solution is purified by anion exchange technology. Uranium in the organic is scrubbed and stripped to effectively purify the uranium so that it contains
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A modified (one-cycle) Purex process has been developed for the separation and recovery of plutonium and uranium from mixed actinide residues. The process utilizes 30 vol % tributyl phosphate--dodecane to extract uranium from a 5M nitric acid-plutonium (III)-uranium(VI) feed. After uranium extraction, plutonium in the aqueous feed solution is purified by anion exchange technology. Uranium in the organic is scrubbed and stripped to effectively purify the uranium so that it contains
Modified Purex Process for the Separation and Recovery of Plutonium-uranium Residues
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Description of Purex Plant Process
Author: E. R. Irish
Publisher:
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.
Publisher:
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.
Thermochemical Measurements of Purex Process Solutions
Author: Glenn A. Burney
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
Nuclear Wastes
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309052262
Category : Science
Languages : en
Pages : 590
Book Description
Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
Publisher: National Academies Press
ISBN: 0309052262
Category : Science
Languages : en
Pages : 590
Book Description
Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
DI-2-Amyl 2-Butylphosphonate as an Extractant for the Recovery of Uranium and Plutonium
Author: Thomas H. Siddall
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20
Book Description
Laboratory Studies on the Use of Uranium(iv) as a Plutonium Reductant in a Purex Process
Author: J. E. Mendel
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 22
Book Description
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 22
Book Description
Purex Process
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The following aspects of the Purex Process are discussed: head end dissolution, first solvent extraction cycle, second plutonium solvent extraction cycle, second uranium solvent extraction cycle, solvent recovery systems, primary recovery column for high activity waste, low activity waste, laboratory waste evaporation, vessel vent system, airflow and filtration, acid recovery unit, fume recovery, and discharges to seepage basin. (LK).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The following aspects of the Purex Process are discussed: head end dissolution, first solvent extraction cycle, second plutonium solvent extraction cycle, second uranium solvent extraction cycle, solvent recovery systems, primary recovery column for high activity waste, low activity waste, laboratory waste evaporation, vessel vent system, airflow and filtration, acid recovery unit, fume recovery, and discharges to seepage basin. (LK).