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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title Influence of Point Defect Evolution on Thermal Conductivity Degradation and Fission Gas Behavior in UO₂ Under Accelerated Irradiation
Author(s) Mutaz Alshannaq, Marat Khafizov
On-Site Speaker (Planned) Mutaz Alshannaq
Abstract Scope The evaluation of thermal properties is essential for understanding nuclear fuel performance. During reactor operation, the buildup of fission products and irradiation-induced lattice defects lead to a degradation in thermal conductivity, hence impacting fuel temperature, and fission gas release (FGR). Despite its importance, the reduction in thermal conductivity caused by point defects (PDs) is not mechanistically modeled in current fuel performance codes (FPCs). In this work, we investigate the effect of PD accumulation described through a rate theory (RT) model on the lattice thermal conductivity of UO₂ and fission gas release (FGR) by modifying the Lucuta thermal conductivity correlation (LC) and investigate their behavior under accelerated conditions. We demonstrate that point defect accumulation, driven by the fission rate, notably reduces thermal conductivity in the cooler rim region. This leads to increased thermal resistance and elevated local temperatures compared to predictions from the standard Lucuta correlation, especially at low burnup.

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A Time Dependent Multiaxial Inelastic Constitutive Model for Nuclear Graphite
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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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