title: Treatment of effluents from uranium oxide production.
abstract: The nuclear fuel cycle comprises a series of industrial processes which involve the production of electricity from uranium in nuclear power reactors. In Brazil the conversion of uranium hexafluoride (UF6) into uranium dioxide (UO2) takes place in Resende (RJ) at the Nuclear Fuel Factory (FCN). The process generates liquid effluents with significant concentrations of uranium, which might be treated before being discharged into the environment. This study investigates the recovery of uranium from three distinct liquid effluents: one with a high carbonate content and the other with an elevated fluoride concentration. This paper also presents a study on carbonate removal from an effluent that consists of a water-methanol solution generated during the filtration of the yellow cake (ammonium uranyl tricarbonate). The results showed that: (1) the uranium from the carbonated solution can be recovered through the ion exchange technique using the strong base anionic resin IRA 910-U, as the carbonate has been removed as CO2 after heating; (2) the most suitable technique to recover uranium from the fluoride solution is its precipitation as (NH4)2UO4F2 (ammonium fluorouranate peroxide), (3) the solution free of carbonate can be added to the fluoride solution and the uranium from the final solution can be recovered by precipitation as ammonium fluorouranate peroxide as well; (4) the carbonate from the water-methanol solution can be recovered as calcium carbonate through the addition of calcium chloride, or it can be recovered as ammonium sulphate through the addition of sulphuric acid. The ammonium sulphate product can be used as a fertilizer.
authors.affiliation: Centre for Development of Nuclear Technology (CDTN / CNEN), Campus da UFMG - Pampulha, Belo Horizonte, MG, Brazil. ana.ladeira.@cdtn.br
authors.forename: A C Q
authors.initials: AC
authors.lastname: Ladeira
authors.forename: J S
authors.initials: JS
authors.lastname: Gonçalves
authors.forename: C A
authors.initials: CA
authors.lastname: Morais
mesh_terms: D000645:Ammonium Sulfate / Q000737:chemistry; D002119:Calcium Carbonate / Q000737:chemistry; D005459:Fluorides / Q000737:chemistry; D007220:Industrial Waste; D007474:Ion Exchange; D000432:Methanol / Q000737:chemistry; D055848:Nuclear Power Plants; D017974:Uranium Compounds / Q000737:chemistry / Q000302:isolation & purification*; D014865:Waste Disposal, Fluid / Q000379:methods*; D014867:Water / Q000737:chemistry
chemical_list: D007220:Industrial Waste; D017974:Uranium Compounds; D014867:Water; D002119:Calcium Carbonate; C047385:uranium oxide; D005459:Fluorides; D000645:Ammonium Sulfate; D000432:Methanol