armi.materials.uraniumOxide module

Uranium Oxide properties.

UO2 is a common ceramic nuclear fuel form. It’s properties are well known. This mostly uses data from 1.

1(1,2,3,4,5,6)

Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation. S.G. Popov, et.al. Oak Ridge National Laboratory. ORNL/TM-2000/351 https://rsicc.ornl.gov/fmdp/tm2000-351.pdf

class armi.materials.uraniumOxide.HeatCapacityConstants(c1, c2, c3, theta, Ea)

Bases: tuple

Create new instance of HeatCapacityConstants(c1, c2, c3, theta, Ea)

Ea

Alias for field number 4

c1

Alias for field number 0

c2

Alias for field number 1

c3

Alias for field number 2

theta

Alias for field number 3

class armi.materials.uraniumOxide.UraniumOxide

Bases: armi.materials.material.FuelMaterial

name = 'Uranium Oxide'

thermalScatteringLaws = (<armi.nucDirectory.thermalScattering.ThermalScattering object>, <armi.nucDirectory.thermalScattering.ThermalScattering object>)

A tuple of ThermalScattering instances with information about thermal scattering.

references = {'heat capacity': 'ORNL/TM-2000/351', 'linear expansion': 'Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation. S.G. Popov, et.al. Oak Ridge National Laboratory. ORNL/TM-2000/351', 'thermal conductivity': 'Thermal conductivity of uranium dioxide by nonequilibrium molecular dynamics simulation. S. Motoyama. Physical Review B, Volume 60, Number 1, July 1999'}

The literature references.

propertyUnits = {'heat capacity': 'J/mol-K'}

theoreticalDensityFrac = 1.0

Thermal conductivity values taken from: Thermal conductivity of uranium dioxide by nonequilibrium molecular dynamics simulation. S. Motoyama. Physical Review B, Volume 60, Number 1, July 1999

thermalConductivityTableK = [300, 600, 900, 1200, 1500, 1800, 2100, 2400, 2700, 3000]

thermalConductivityTable = [7.991, 4.864, 3.64, 2.768, 2.567, 2.294, 2.073, 1.891, 1.847, 1.718]

heatCapacityConstants = HeatCapacityConstants(c1=302.27, c2=0.008463, c3=87410000.0, theta=548.68, Ea=18531.7)

enrichedNuclide = 'U235'

Name of enriched nuclide to be interpreted by enrichment modification methods

adjustTD(val: float) → None

getTD() → float

applyInputParams(U235_wt_frac: Optional[float] = None, TD_frac: Optional[float] = None, *args, **kwargs) → None

Apply optional class 1/class 2 custom enrichment input.

Notes

This is often overridden to insert customized material modification parameters but then this parent should always be called at the end in case users want to use this style of custom input.

This is only applied to materials considered fuel so we don’t apply these kinds of parameters to coolants and structural material, which are often not parameterized with any kind of enrichment.

setDefaultMassFracs() → None

UO2 mass fractions. Using Natural Uranium without U234

meltingPoint()

Melting point in K

From 1.

density(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Density in (g/cc)

Polynomial line fit to data from 1 on page 11.

thermalConductivity(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Thermal conductivity

Ref: Thermal conductivity of uranium dioxide by nonequilibrium molecular dynamics simulation. S. Motoyama. Physical Review B, Volume 60, Number 1, July 1999

linearExpansion(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Linear expansion coefficient.

Curve fit from data in 1

linearExpansionPercent(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Return dL/L

From Section 3.3 of 1

heatCapacity(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Heat capacity in J/kg-K.

From Section 4.3 in 1

paramCollectionType

alias of armi.reactor.parameters.parameterCollections.FuelMaterialParameterCollection

class armi.materials.uraniumOxide.UO2

Bases: armi.materials.uraniumOxide.UraniumOxide

Another name for UraniumOxide

paramCollectionType

alias of armi.reactor.parameters.parameterCollections.FuelMaterialParameterCollection