عنوان مقاله [English]
نویسنده [English]چکیده [English]
In this paper, for recovery and purification of uranium from slag, three simple processes including thermal treatment in low temperature and leaching process in ambient temperature, and finally precipitation of uranium and combined method is suggested and the role of each process on purification of the product is investigated. In thermal treatment, hard dissolving U+4 in slag was oxidized to easy dissolving uranium. The uranium was then separated from solid phase through leaching process using diluted nitric acid, ammonium bicarbonate, and methanol solutions. So leached uranium was precipitated in the form of ADU(ammonium diuranate) and AUC(ammonium uranyl carbonate) with high degree of purity in presence of fluoride ions, and very pure U3O8 with fluoride concentration less than the permitted limit in nuclear fuel is then prepared. The results of analysis show that in produced U3O8, impurities that affect uranium enrichment process and fuel performance are decreased under the permitted limit.