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Uranium nitride

Names
IUPAC name Uranium nitride
Identifiers
CAS Number	12033-83-9
Properties
Chemical formula	U2N3
Molar mass	518.078 g/mol
Appearance	crystalline solid
Density	11300 kg m-3, Solid
Melting point	900°C (decomposes to UN)
Boiling point	Decomposes
Solubility in water	0.08 g/100 ml (20 °C)
Structure
Crystal structure	Hexagonal, hP5
Space group	P-3m1, No. 164
Except where otherwise noted, data are given for materials in their standard state (at 25 °C , 100 kPa). Y verify (what is  ?) Infobox references

Uranium nitride refers to a family of several ceramic compounds: uranium mononitride (UN), uranium sesquinitride (U₂N₃), which exists in either an alpha or beta phase, and uranium dinitride (UN₂).

Uranium mononitride is used as nuclear fuel in some nuclear test reactors, because it has some properties similar to uranium dioxide or uranium carbide. The property which makes uranium mononitride highly attractive as a nuclear fuel is its thermal conductivity, which is on the order of 4-8 times higher than that of uranium dioxide, the most commonly used nuclear fuel, at typical operating temperatures. Increased thermal conductivity results in lower thermal gradients between inner and outer sections of the fuel, potentially allowing for higher operating temperatures and reducing macroscopic restructuring of the fuel, which limits fuel lifetime.

Uranium nitride can be synthesized by the reaction of nitrogen with uranium at 700 K. Uranium nitride may be formed as a minor product of uranium combustion in air; however, the more thermodynamically stable uranium dioxide will be the major product.

According to an article in "Nuclear Engineering International", uranium nitride (enriched to less than 20% U-235) is the fuel chosen by Hyperion Power Generation to fuel their recently revised Hyperion Power Module. This article, however, incorrectly states that uranium sesquinitride will be used, rather than uranium mononitride. The correct information is available at http://www.nrc.gov/reactors/advanced/hyperion.html

References

1. R. B. Matthews, K. M. Chidester, C. W. Hoth, R. E. Mason, R. L. Petty (1988). "Fabrication and testing of uranium nitride fuel for space power reactors". Journal of Nuclear Materials. 151 (3): 345. doi:10.1016/0022-3115(88)90029-3.{{cite journal}}: CS1 maint: multiple names: authors list (link)
2. Cotton, Simon (1991) Lanthanides and Actinides. New York: Oxford University Press, p. 126
3. Staff (2009-11-20). "Hyperion launches U2N3-fuelled, Pb-Bi-cooled fast reactor". Nuclear Engineering International. Global Trade Media, a division of Progressive Media Group Ltd. Retrieved 29 November 2009.

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