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Ammonium Uranyl Carbonate MSDS
Tetraammonium uranyl tricarbonate, of uranium depleted in uranium 235 |
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| Formula | (NH4)4(UO2)(CO3)3 |
| Structure | ![]() |
| Uses | Substance is used in uranium yellow glazes. |
| Registry Numbers and Inventories. | |
| CAS | 18077-77-5 |
| NIH PubChem CID | 3015006 |
| EC (EINECS/ELINCS) | 241-988-5 |
| UN (DOT) | 2909 |
| Merck | 12,602 |
| Beilstein/Gmelin | NA |
| Properties. | |
| Formula | C3H16N4O11U |
| Formula mass | 522.21 |
| Hazards and Protection. | |
| Storage | Keep in a cool, dry, dark location in a tightly sealed container or cylinder. Keep away from incompatible materials, ignition sources and untrained individuals. Secure and label area. Protect containers/cylinders from physical damage. |
| Handling | All chemicals should be considered hazardous. Avoid direct physical contact. Use appropriate, approved safety equipment. Untrained individuals should not handle this chemical or its container. Handling should occur in a chemical fume hood. |
| Protection | Wear appropriate protective gloves, clothing and goggles. |
| Respirators | Wear positive pressure self-contained breathing apparatus (SCBA). |
| Small spills/leaks | Do not touch damaged packages or spilled material. Cover liquid spill with sand, earth or other noncombustible absorbent material. Cover powder spill with plastic sheet or tarp to minimize spreading. Contact radiation safety officer. |
| Stability | No data. |
| Fire. | ||||
| Fire fighting | Presence of radioactive material will not influence the fire control processes and should not influence selection of techniques. Small Fires: Dry chemical, carbon dioxide, water spray or regular foam. Large Fires: Water spray, fog (flooding amounts). | |||
| Fire potential | May burn but does not ignite readily. | |||
| Health. | |
| Exposure effects | |
| Ingestion | See Inhalation. |
| Inhalation | Minimal risk if packaging remains intact. Package damage can result in a measurable release of radiation but the risk is still low. |
| Skin | See Inhalation. |
| Eyes | See Inhalation. |
First aid |
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| Ingestion | Medical problems take priority over radiological concerns. Use first aid treatment according to the nature of the injury. Do not delay care and transport of a seriously injured person. |
| Inhalation | Apply artificial respiration if victim is not breathing. Administer oxygen if breathing is difficult. See Ingestion. |
| Skin | Immediately flush with running water for at least 20 minutes. See Ingestion. |
| Eyes | Immediately flush with running water for at least 20 minutes. See Ingestion. |
| Transportation | ||
| UN number | 2909 | ![]() |
| Response guide | 161 | |
| Hazard class | 7 | |
| USCG CHRIS Code | RAD | |
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Ammonium uranyl carbonate |
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IUPAC name |
uranium(VI)dioxide di-ammonium carbonate |
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Other names |
uranyl ammonium carbonate |
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Properties |
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Molecular formula |
UO2CO3·2(NH4)2CO3 |
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Molar mass |
522.199 g/mol |
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Melting point |
Decomposes between 165°C and 185°C |
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Solubility in water |
Insoluble |
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Except
where noted otherwise, data are given for |
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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 powdwer. The ex-AUC uranium dioxide powder is free-flowing, relatively coarse (10 µ) and porous with specific surface area in the range of 5m2/g and suitable for direct pelletisation, avoiding the granulation step. Conversion to UO2 is often performed as the first stage of nuclear fuel fabrication.
The AUC process is followed in South Korea and Argentina. In the AUC route, calcination, reduction and stabilization are simultaneously carried out in a vertical fluidized bed reactor. In most countries, sinterable grade UO2 powder for nuclear fuel is obtained by the ammonium diuranate (ADU) process, which requires several more steps.
Ammonium uranyl carbonate is also one of the many forms called yellowcake in this case it is the product obtainded by the heap leach process.
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