Development of the Port Radium Leaching Process For Recovery of Uranium.
Read Online

Development of the Port Radium Leaching Process For Recovery of Uranium.

  • 895 Want to read
  • ·
  • 28 Currently reading

Published by s.n in S.l .
Written in English

Book details:

Edition Notes


SeriesCanada Mines Branch Technical Paper -- 13
ID Numbers
Open LibraryOL21893261M

Download Development of the Port Radium Leaching Process For Recovery of Uranium.


  A. Thunaes et al.: “Development of the Port Radium Leaching Process for Recovery of Uranium,” Canadian Department of Mines and Technical Surveys, Ottawa, Mines Branch Technical Paper TP 13, Google ScholarAuthor: F. C. Lendrum. Table of ContentsRadium MeasurementsApproximate Method for SolidsGamma-Ray Measurement of RadiumRadium Determination by Emanation MethodProcedure when Radium is Soluble or in SolutionTreatment for Solution Containing Barium in Excess over RadiumTreatment for Solutions Containing Little or no BariumTreatment for Solution without Barium & Excess Barium . This paper deals with materials of construction and problems encountered and overcome in leaching and filtration of oxidized sulphuric acid slurry in the Port Radium mill after eight years of operation. The slurry is characterized by a high calcium sulphate content as well as a high chloride level under oxidized conditions, both of which. Uranium processing - Uranium processing - Leaching: Roasted uranium ores are leached of their uranium values by both acidic and alkaline aqueous solutions. For the successful operation of all leaching systems, uranium must either be initially present in the more stable hexavalent state or be oxidized to that state in the leaching process. Acid leaching is commonly performed by agitating an .

Over the past 60 years of uranium process development only a few commercial uranium plants have adopted a pressure leaching process in their flowsheet. The selection of acid versus alkaline pressure leaching is related to the uranium and gangue mineralogy. Tetravalent (U+4) uranium has to be oxidized to hexavalent (U+6) uranium to be soluble. In-situ leach is a new technological development that began in During this time the techniques, methods and equipment for the process from basic concepts to successful commercial realisation had to be developed. These are the aspects that could determine the characteristics of the In-Situ Leaching (ISL) process.   In the heap leach process, the ore is placed on a engineered barrier and sprayed with acid. The uranium dissolves into solution and is collected at the engineered barrier. The solution undergoes additional chemical processing to produce "yellowcake". In the in-situ recovery (ISR) process, a solution called lixiviant (typically containing water mixed with oxygen and/or hydrogen . Removal of radium and thorium In situ and in place leaching Ill Process development Materials of construction Recovery of uranium from phosphoric acid Introduction Processes for uranium recovery from phosphoric acid References CHAPTER 8. PRODUCT RECOVERY

Provided is a process for recovering metals from solid radioactive waste, preferably uranium, cesium, mercury, thorium, rare earths or combinations thereof. The process comprises a leaching step and a separation step. The leaching step comprises contacting the solid radioactive waste with an aqueous inorganic acid and a leaching salt to produce a mixture of a metal-rich leachate and a metal. Recovery of uranium by heap leaching is less common, with acid heap leaching used in Hungary (NEA/IAEA, ) and and alkaline heap leaching process used in Namibia (Schnell, ). Heap leaching today is applied to crushed ores, and modern heaps are designed to prevent ground contamination using a minimum of double containment, groundwater. Nitric acid leaching method has been applied to the decontamination process, while TBP/n-dodecane extraction method to the refining and recovery of uranium from the leaching nitric acid solution. The results of laboratory scale experiments show that large uranium decontamination more» factors (> 10{sup 3}) are obtained on the simulated sludges. It was found that the low temperature of the bioleaching process, which was restricted to 35 °C, resulted in such slow uranium extraction rates that the process could not compete with the conventional atmospheric acid-ferric leach process, despite the advantages that it held: pyrite oxidation provided acid and ferric sulfate, and liberated.