Zirconium(IV) fluoride

Zirconium(IV) fluoride
Identifiers
CAS number 7783-64-4 Y
15298-38-1 (monohydrate)
ChemSpider 74196 Y
Jmol-3D images Image 1
Properties
Molecular formula ZrF4
Molar mass 167.21 g/mol
Appearance white crystalline powder
Density 4.43 g/cm3 (20 °C)
Melting point

910 °C

Solubility in water 1.32 g/100mL (20 °C)
1.388 g/100mL (25 °C)
Structure
Crystal structure Monoclinic, mS60
Space group C12/c1, No. 15
Hazards
EU Index Not listed
Flash point Non-flammable
LD50 98 mg/kg (oral, mouse)
Related compounds
Other anions Zirconium(IV) chloride
Zirconium(IV) bromide
Zirconium(IV) iodide
Other cations Titanium(IV) fluoride
Hafnium(IV) fluoride
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Except where noted otherwise, data are given for materials in their standard state (at 25 °C, 100 kPa)
Infobox references

Zirconium(IV) fluoride (ZrF4) is an inorganic chemical compound. It is a component of ZBLAN fluoride glass. It is insoluble in water. It is the main component of fluorozirconate glasses.

Three crystalline phases of ZrF4 have been reported, α (monoclinic, β (tetragonal, Pearson symbol tP40, space group P42/m, No 84) and γ (unknown structure). β and γ phases are unstable and irreversibly transform into the α phase at 400 °C.[1]

Zirconium fluoride is used as a zirconium source in oxygen-sensitive applications, e.g. metal production.[2] Zirconium fluoride can be purified by distillation or sublimation.[3]

Conditions/substances to avoid are: moisture, active metals, acids and oxidizing agents.

Zirconium fluoride in a mixture with other fluorides is a coolant for molten salt reactors. In the mixture with sodium fluoride it is a candidate coolant for the Advanced High-Temperature Reactor.

Together with uranium salt, zirconium fluoride can be a component of fuel-coolant in molten salt reactors. Mixture of sodium fluoride, zirconium fluoride, and uranium tetrafluoride (53-41-6 mol.%) was used as a coolant in the Aircraft Reactor Experiment. A mixture of lithium fluoride, beryllium fluoride, zirconium fluoride, and uranium-233 tetrafluoride was used in the Molten-Salt Reactor Experiment. (Uranium-233 is used in the thorium fuel cycle reactors.)

References

  1. ^ Paul L. Brown, Federico J. Mompean, Jane Perrone, Myriam Illemassène (2005). Chemical thermodynamics of zirconium. Gulf Professional Publishing. p. 144. ISBN 0-444-51803-7. http://books.google.com/books?id=DvqwTdVhjMEC&pg=PA144. 
  2. ^ "Zirconium fluoride". American elements. http://www.americanelements.com/zrf.html. Retrieved 2009-07-07. 
  3. ^ "Method for preparing ultra-pure zirconium and hafnium tetrafluorides. United States Patent 4578252". http://www.freepatentsonline.com/4578252.html. Retrieved 2009-07-07.