Zirconium tetrafluoride

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Zirconium(IV) fluoride
Zirconium(IV) fluoride
Identifiers
CAS number 7783-64-4 YesY
15298-38-1 (monohydrate)
ChemSpider 74196 YesY
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
Except where noted otherwise, data are given for materials in their standard state (at 25 °C (77 °F), 100 kPa)
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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[edit]

  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. 
  2. ^ "Zirconium fluoride". American Elements. Retrieved 2009-07-07. 
  3. ^ "Method for preparing ultra-pure zirconium and hafnium tetrafluorides. United States Patent 4578252". Retrieved 2009-07-07.