首页>
外国专利>
Dissolution of uranium-molybdenum and/or uraniummolybdenum-plutonium reactor fuel elements
Dissolution of uranium-molybdenum and/or uraniummolybdenum-plutonium reactor fuel elements
展开▼
机译:铀钼和/或铀钼p反应堆燃料元件的溶解
展开▼
页面导航
摘要
著录项
相似文献
摘要
Uranium and/or plutonium values are recovered from uranium and/or plutonium molybdenum compositions by treating the mixture at 375-600 DEG C. with a 10-60% hydrogen chloride gas and air mixture producing a volatile molybdenum oxychloride and a non-volatile uranium product, mainly oxides, which is then dissolved in nitric acid yielding stable uranium nitrate solution. The uranium values obtained from the first stage may be treated with hydrogen chloride gas to remove further molybdenum before dissolving in nitric acid. Chlorine impurity may be removed from the oxychlorination mixture by heating in air containing up to 3% of water to volatilize chlorine impurity. The uranium/molybdenum mixture is carried in aluminium or zirconium or stainless steel cans which are removed before treatment of the composition by using chlorine or hydrogen chloride gas at temperatures of approximately 600 DEG C.
展开▼