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, armi.materials.material.SimpleSolid

name = 'Uranium Oxide'

String identifying the material

enrichedNuclide = 'U235'

Name of enriched nuclide to be interpreted by enrichment modification methods

REFERENCE_TEMPERATURE = 27

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

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

propertyValidTemperature = {'density': ((300, 3100), 'K'), 'heat capacity': ((298.15, 3120), 'K'), 'linear expansion': ((273, 3120), 'K'), 'linear expansion percent': ((273, 3123.0), 'K'), 'thermal conductivity': ((300, 3000), 'K')}

Dictionary of valid temperatures over which the property models are valid in the format ‘Property Name’: ((Temperature_Lower_Limit, Temperature_Upper_Limit), Temperature_Units)

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'}

citation}

Type

The literature references {property

theoreticalDensityFrac = 1.0

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

A tuple of ThermalScattering instances with information about thermal scattering.

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]

adjustTD(val: float) → None

getTD() → float

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

setDefaultMassFracs() → None

UO2 mass fractions. Using Natural Uranium without U234

meltingPoint()

Melting point in K

From 1.

density3(Tk: Optional[float] = None, Tc: Optional[float] = None) → float

Density in (g/cc)

Polynomial line fit to data from 1 on page 11.

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

Heat capacity in J/kg-K.

From Section 4.3 in 1

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

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

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