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Dissolution of uranium-molybdenum and/or uraniummolybdenum-plutonium reactor fuel elements

机译:铀钼和/或铀钼p反应堆燃料元件的溶解

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.
机译:通过用10-60%的氯化氢气体和空气混合物在375-600℃下处理该混合物,从铀和/或p钼组合物中回收铀和/或values的值,产生挥发性的三氯氧化钼和非挥发性的铀。产物,主要是氧化物,然后将其溶于硝酸,得到稳定的硝酸铀溶液。在溶解于硝酸之前,可以用氯化氢气体处理从第一阶段获得的铀值,以除去更多的钼。可以通过在最多含3%的水的空气中加热以除去氯杂质,从而从氯氯化混合物中除去氯杂质。铀/钼混合物装在铝或锆或不锈钢罐中,在用约600℃的温度下使用氯气或氯化氢气体处理组合物之前,将其除去。

著录项

  • 公开/公告号GB981532A

    专利类型

  • 公开/公告日1965-01-27

    原文格式PDF

  • 申请/专利权人 UNITED STATES ATOMIC ENERGY COMMISSION;

    申请/专利号GB19620001418

  • 发明设计人

    申请日1962-01-15

  • 分类号C01G43;C07C19/04;C22B60/02;G21C19/44;G21C19/48;

  • 国家 GB

  • 入库时间 2022-08-23 15:34:09

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