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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title Development, Validation, and Uncertainty Quantification of a BISON Model for Pd Penetration in TRISO Particle Fuels
Author(s) Chaitanya V. Bhave, Jacob Hirschhorn, Som LakshmiNarasimha Dhulipala, Mathew Swisher, Ryan Sweet
On-Site Speaker (Planned) Chaitanya V. Bhave
Abstract Scope TRISO particle fuels use SiC as the main barrier against metallic fission product (FP) release. Pd penetration weakens the SiC layer, increasing stress and degrading integrity, which threatens the containment of radioactive FPs. Traditional temperature-dependent correlations for predicting Pd penetration rely on experimental data with significant scatter due to varying conditions like burnup, SiC microstructure, and irradiation times. This variability complicates fuel qualification and licensing for reactors with different operating conditions. A new mechanistic reduced order model is developed to predict Pd penetration using insights from atomistic and mesoscale modeling. This model is validated against historical data, and Bayesian uncertainty quantification is used to reduce the model inadequacy of the ROM. The model is implemented in the Multiphysics Object Oriented Simulation Environment (MOOSE) within the BISON engineering scale performance code. The developed models will support the utilization of BISON in fuel performance modeling of TRISO fuels for advanced reactors.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Time Dependent Multiaxial Inelastic Constitutive Model for Nuclear Graphite
Bridging Distributed Autonomous Platforms for Materials Innovation
Comparative Assessment of Biaxial Creep Anisotropy in ZIRLOŽ and HANA-4 Zirconium Alloys: Influence of Microstructure and Processing
Corrosion of Ni-based alloys in Light Water Reactor Environment: An In-situ Bragg Coherent Diffraction Imaging approach
Coupled Experimental and Modeling of the Interactions Between Dislocations, Precipitates, and Grain Boundaries from Atomic to Mesoscale
Development, Validation, and Uncertainty Quantification of a BISON Model for Pd Penetration in TRISO Particle Fuels
Gamma Ray Shielding Performance of 3D Printed Polymers
High-Temperature Corrosion of Pure Vanadium in Molten Chloride Salt Environments
In-Situ and 3D Measurements of Dynamic Processes in Nuclear Materials Utilizing Synchrotron High-energy X-rays
Influence of Point Defect Evolution on Thermal Conductivity Degradation and Fission Gas Behavior in UO₂ Under Accelerated Irradiation
Quantifying Amorphous Fractions using Different Characterization Techniques
Radiation-Induced Amorphization in WO₃ and MoO₃: Structural Response
Statistical Effects of Carbon on Primary Radiation Damage and Initial Clustering of Defects in Austenitic Stainless Steel
Strain Field Evolution Around MX Precipitates in a Ferrite Matrix After Neutron Irradiation at 490°C to 7.4 dpa
Ultra-High Temperature Thermal Characterization of Materials for Nuclear Applications
Unique Aspects of Coupling Experiment and Modeling in Understanding Irradiation Behavior of Nuclear Materials

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