Fuel Performance Models

commentnote:Acknowledgement

The modeling approach introduced here was developed based on the baseline Sodium-cooled Fasted Reactor (SFR) metallic fuel performance models in BISON, which are described in details in (Matthews et al., 2023).

Geometry and Mesh

The 2D-RZ meshes for the X447 pins are generated with the intrinsic rodlet meshing capability in BISON's FIPDRodletMeshGenerator. The mesh generator directly reads the pin design parameter CSV file and generates the mesh along with a series of MeshMetaData to help ensure consistent use of pin geometry data throughout the simulations. Lower-dimensional elements are then added to the fuel and cladding contact surface sidesets with LowerDBlockFromSidesetGenerator, which is automated by the corresponding Contact Action used in this model. These additional side elements serve as contact surfaces for the Lagrange multiplier variables parameterizing mortar contact.

Material and Behavioral Models

The following material and behavioral models for the U-10Zr fuel are used in this VTB model. Note that Automatic differentiation is used in this model, as indicated by the "AD" prefix.

Fuel Performance BehaviorBISON ModelDescription
ElasticityADUPuZrElasticityTensorIsotropic elastic mechanical properties for SFR metallic fuels
Creep DeformationADUPuZrCreepUpdateCreep correlation of SFR metallic fuels
Fission Gas SwellingADSimpleFissionGasViscoplasticityStressUpdateCalculates the change in volume due to gaseous fission product production in SFR metallic fuels
Solid Fission Product SwellingADBurnupDependentEigenstrainCalculates the change in volume due to solid fission product production in SFR metallic fuels
Fission Density RateADUPuZrFissionRateComputes fission density rate based on linear power, axial power profile, fuel geometry, and Pu/Zr concentrations
BurnupADUPuZrBurnupComputes the burnup for SFR metallic fuels
Specific Heat/Thermal ConductivityADUPuZrThermalCalculates the thermal conductivity and specific heat for SFR metallic fuels
Thermal ExpansionADUPuZrThermalExpansionEigenstrainComputes an eigenstrain due to thermal expansion for SFR metallic fuels using a function that describes the mean thermal expansion as a function of temperature
Fission Gas ReleaseADSimpleFissionGasViscoplasticityStressUpdateFission gas release model for SFR metallic fuels is handled by the fission gas swelling model
Hot PressingADUPuZrHotPressingStressUpdateComputes the inelastic strain of UPuZr metallic fuel due to hot pressing
Sodium LoggingADUPuZrSodiumLoggingComputes the local fractional amount of sodium logging that can be used to evaluate thermal conductivity recovery

The following material and behavioral models for the HT9 cladding were used in this VTB model:

Cladding Performance BehaviorBISON ModelDescription
ElasticityADHT9ElasticityTensorElastic mechanical properties for HT9
Creep DeformationADHT9CreepUpdateIrradiation creep and thermal creep (including primary, secondary and tertiary stages) correlations for HT9
Volumetric SwellingNeglectedVolumetric Swelling of HT9 is neglected. As a tempered martensitic steel, HT9 does not swell as prominently as its austenitic stainless steel counterparts (i.e., 316SS and D9).
Thermal ExpansionADComputeThermalExpansionEigenstrainThermal expansion model with constant instantaneous thermal expansion coefficient
Specific Heat/Thermal ConductivityADHT9ThermalCalculates the thermal conductivity and specific heat for HT9 cladding
Cladding DamageHT9FailureCladCladding damage model for HT9 cladding based on the steady-state Cumulative Damage Fraction (CDF) model to facilitate failure determination
FCCIADMetallicFuelWastageCalculates the FCCI wastage thickness that is used to reduce effective cladding thickness
CCCIADMetallicFuelCoolantWastageCalculates the CCCI wastage thickness that is used to reduce effective cladding thickness

As briefly mentioned above, some advanced MOOSE features, such as Automatic Differentiation and mortar contact model, are employed by this VTB model. The mortar contact method was implemented for contact between the inner radial surface of the cladding and outer radial surfaces of the fuel. Both normal and tangential mechanical contact are modeled, with tangential contact including considerations of friction between the contact surfaces, parameterized by a friction coefficient, . A value of =0.1 was determined to as it leads to axial fuel growth values consistent with PIE observation.

Additionally, MetallicFuelWastageDegradationFunction is used to generate axial-dependent functions based on the FCCI/CCCI wastage thickness profiles recorded by corresponding VectorPostprocessors. Such functions are directly used by cladding mechanical properties to artificially soften the cladding strength.

References

  1. Christopher Matthews, Stephen Novascone, Al Casagranda, Larry Aagesen, Cetin Unal, and David Andersson. Development and formulation of physics based metallic fuel models and comparison to integral irradiation data. Journal of Nuclear Materials, 578:154343, 2023.[BibTeX]