Uranium Nitride

Fuels

Density: 14.32 g/cm³

Uranium mononitride fuel at 5% U-235 enrichment. High uranium density and thermal conductivity make it attractive for advanced reactors.

Composition

Nuclide / Element	Fraction
U-235	0.025000
U-238	0.475000
N-14	0.500000

Code output

MCNP

c Uranium Nitride (5 wt% U-235)
c Density: 14.32 g/cm3 (use -14.32 on cell card)
m6    92235.80c  0.025000  $ U-235
      92238.80c  0.475000  $ U-238
       7014.80c  0.500000  $ N-14

SCONE reads ACE libraries: build nuclearData.materials entries from these nuclides using ZAID plus a temperature/table suffix that exists in your aceLibrary, with number densities in atoms/barn-cm. See the SCONE nuclear data tutorial and the NRDP library reference.

Notes

N-15 enrichment is sometimes used to reduce parasitic (n,p) reactions on N-14. Replace N-14 with N-15 (7015.80c) if modeling N-15-enriched UN.

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