Ammonium uranyl carbonate

（重定向自Uranyl ammonium carbonate）

Ammonium uranyl carbonate (UO₂CO₃·2(NH₄)₂CO₃) is known in the uranium processing industry as AUC and is also called uranyl ammonium carbonate. This compound is important as a component in the conversion process of uranium hexafluoride (UF₆) to uranium dioxide (UO₂). The ammonium uranyl carbonate is combined with steam and hydrogen at 500–600 °C to yield UO₂. In another process aqueous uranyl nitrate, known as uranyl nitrate liquor (UNL) is treated with ammonium bicarbonate to form ammonium uranyl carbonate as a solid precipitate. This is separated from the solution, dried with methanol and then calcinated with hydrogen directly to UO₂ to obtain a sinterable grade powder. The ex-AUC uranium dioxide powder is free-flowing, relatively coarse (10 µ) and porous with specific surface area in the range of 5 m/g and suitable for direct pelletisation, avoiding the granulation step. Conversion to UO₂ is often performed as the first stage of nuclear fuel fabrication.

单词	Uranyl ammonium carbonate
释义	Uranyl ammonium carbonate 英语百科 Ammonium uranyl carbonate （重定向自Uranyl ammonium carbonate） Ammonium uranyl carbonate (UO₂CO₃·2(NH₄)₂CO₃) is known in the uranium processing industry as AUC and is also called uranyl ammonium carbonate. This compound is important as a component in the conversion process of uranium hexafluoride (UF₆) to uranium dioxide (UO₂). The ammonium uranyl carbonate is combined with steam and hydrogen at 500–600 °C to yield UO₂. In another process aqueous uranyl nitrate, known as uranyl nitrate liquor (UNL) is treated with ammonium bicarbonate to form ammonium uranyl carbonate as a solid precipitate. This is separated from the solution, dried with methanol and then calcinated with hydrogen directly to UO₂ to obtain a sinterable grade powder. The ex-AUC uranium dioxide powder is free-flowing, relatively coarse (10 µ) and porous with specific surface area in the range of 5 m/g and suitable for direct pelletisation, avoiding the granulation step. Conversion to UO₂ is often performed as the first stage of nuclear fuel fabrication.
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