Ammonium Uranyl Carbonate MSDS


Ammonium Uranyl Carbonate MSDS

 

Tetraammonium uranyl tricarbonate, of uranium
depleted in uranium 235

 

  • Uranate(4-), tris[carbonato(2-)-O,O’]dioxo-, tetraammonium,
    (HB-8-22-111’1’1”1”)
  • Azanium uranium carbonate
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  
   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 radiation 7
Response guide 161
Hazard class 7
USCG CHRIS Code RAD

 


Ammonium uranyl
carbonate


IUPAC name


uranium(VI)dioxide di-ammonium carbonate

Other
names

uranyl
ammonium carbonate

Properties


Molecular formula

UO2CO3·2(NH4)2CO3


Molar mass

522.199
g/mol


Melting point

Decomposes between 165°C and 185°C



Solubility
in water


Insoluble

Except
where noted otherwise, data are given for

materials in their standard state

(at 25 °C, 100 kPa)

Infobox disclaimer and references

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 obtained by the heap leach process.

 

 

radiation 7
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