Author: G. I. CathersPublisher:
ISBN:
Category : Fused salts
Languages : en
Pages : 14
Book Description
Recovery of Uranium from Highly Irradiated Reactor Fuel by Fused Salt --
Author: G. I. CathersPublisher:
ISBN:
Category : Fused salts
Languages : en
Pages : 14
Book Description
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.
Use of Fused Salt-fluoride Volatility Process with Irradiated Urania Decayed 15-30 Days
Author: G. I. CathersPublisher:
ISBN:
Category : Fission products
Languages : en
Pages : 34
Book Description
Fused-salt Fluoride-volatility Process for Recovering Uranium from Spent Aluminum-based
Author: The Fused Salt-fluoride Volatility Process for Recovering Uranium
Author: G. I. GathersPublisher:
ISBN:
Category : Fused salt electrolysis
Languages : en
Pages : 40
Book Description
Recovery of Uranium from Spent Zirconium-based Reactor Fuels in the Oak Ridge Volatility Pilot Plant
Author: 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).
Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials
Author: A Process for the Recovery of Uranium from Nuclear Fuel Elements Using Fluid-bed Drying and Volatility Techniques
Author: Publisher:
ISBN:
Category : Nuclear fuel
Languages : en
Pages :
Book Description
A process scheme for the recovery of uranium from fuel elements has been developed. The scheme combines continuous fluid-bed drying and fluoride volatility techniques after initial dissolution of the fuel element in the appropriate aqueous system, hence the designation ADF, Aqueous Dry Fluorination Process. The application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels is described. ln the process, the feed solution is sprayed horizontally through a two-fluid nozzle and is atomized directly in the heated fluidized bed. The spray droplets are dried on the fluidized particles and form a dense coating. Excessive particle growth was limited by the use of air attrition-jets inserted directly in the bed. Aqueous hydrofluoric acid solutions containing leaves2 to 3.6 M zirconiuni, 0.007 to 0.03 M uranium, and free acid concentrations from 1 to about l0 M were successfully processed in a 6-in.-diameter Inconel fluid-bed spray dryer. Rates equivalent to about 3.l kg/hr of zirconium were achieved, 160 ml/min with the most concentrated feed solution. Experiments were successfully carried out from 240 to 450 deg C.A new design for a two-fluid nozzle was developed. Extensive work was done to identify the various zirconium fluoride compounds formed. The granular dryer product was subsequently fluorinated at temperatures to 600 deg C in fluid beds and to 700 deg C in static beds to remove the uranium as the volatile hexafluoride. About 90 to 95% uranium removal was consistently achieved near 600 deg C. The relatively low uranium recovery under these conditions is a disadvantage for the application to zirconium-base fuels. It was found necessary to resort to static beds and higher temperatures to achieve greater removal. Since the fluorine attack on nickel, the material of construction, is prohibitive at temperatures above 600 deg C, a disposable fluorinator concept for use with static beds is described. Results of corrosion studies are reported. A preliminary chemical flowsheet with a design capacity of 1l00 kg of uranium (93% enriched) annually is presented. (auth).
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