Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
URANIUM RECOVERY FOR SPENT FUEL BY DISSOLUTION IN FUSED SALT AND FLUORINATION.
Author: Fused-salt Fluoride-volatility Process for Recovering Uranium from Spent Aluminum-based
Author: Recovery of Uranium from Spent Zirconium-based Reactor Fuels in the Oak Ridge Volatility Pilot Plant
Author: Recovery of Uranium from Highly Irradiated Reactor Fuel by a Fused Salt--fluoride Volatility Process
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Volatility processing is a promising new nonaqueous method for recovering uranium from heterogeneous reactor fuels containing zirconium and from molten fluoride fuels. it is potentially applicable to other types of reactor fuels not amenable to aqueous dissolution and subsequent solvent extraction processing. Amond the attractive features of the fused salt-fluoride volatility process are the small volume of the fission product waste, which is in solid form; the form of product, UF6; and virtual elimination of the need for criticality control. the main disadvantages are the high temperatures used and the high equipment corrosion. The paper discusses the processes under development.
The Fused Salt-fluoride Volatility Process for Recovering Uranium
Author: G. I. GathersPublisher:
ISBN:
Category : Fused salt electrolysis
Languages : en
Pages : 40
Book Description
A FUSED SALT-FLUORIDE VOLATILITY PROCESS FOR RECOVERY AND DECONTAMINATION OF URANIUM.
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A preliminary chemical flowsheet is presented of a fluoride volatility process for recovering and decontaminating U from heterogeneous reactor fuels after dissolution in a fused salt. In laboratory work, a gross BETA decontamination factor of>10/sup 4/ was obtained in the fluorination of a UF/sub 4/-- NaF-- Zr F/sub 4/ melt by passing the product UF/sub 6/ through NaF at 650 deg C. The solubility of UF/sub 6/ in molten NaF--ZrF/sub 4/ was shown in kinetic studies to cause a lag in the evolution of UF/sub 6/ from the fluorinator. Corrosion of nickel in the fluorination step appeared to be 2 to 4 mils/hr during the time that U was present. The average corrosion rate over the process as a whole yvas less than 0.4 mil/hr. (auth).
Spray Fluorination of Fused Salt as a Uranium Recovery Process
Author: Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts
Author: National Research CouncilPublisher: National Academies Press
ISBN: 0309174929
Category : Science
Languages : en
Pages : 147
Book Description
This book discusses the technical alternatives for cleanup of radioactive fluoride salts that were the fuel for the Molten Salt Reactor Experiment, a novel nuclear reactor design that was tested in the 1960s at the Oak Ridge National Laboratory in Tennessee. These fluoride salts pose an unusual cleanup challenge. The book discusses alternatives for processing and removing the salts based on present knowledge of fluoride salt chemistry and nuclear reactions of the radioactive constituents.
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
Author: P. BurnPublisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 62
Book Description
Nuclear Wastes
Author: National Research CouncilPublisher: 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.