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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Author(s) Elina Charatsidou, Maria Giamouridou, Nils Wikström, Robert Frost, Gyula Nagy, Petter Ström, Daniel Primetzhofer, Pär Olsson
On-Site Speaker (Planned) Elina Charatsidou
Abstract Scope Characterization of mechanical and thermophysical properties of nuclear fuels under irradiation is essential in understanding their behavior and predicting their performance. This study investigated defects induced by proton irradiation and ion implantation and the in-situ degradation of the thermal properties of UN and composite fuels under various temperatures and doses. Solid (Zr, Ba) and gaseous (Kr, Xe) elements, representing fission products, were implanted in UN pellets to study microstructural, mechanical, and thermal degradation. However, during the implantation significant oxygen contamination on UN was introduced resulting in surface oxidation, affecting the possibility for further surface-sensitive studies. Additionally, during post irradiation characterization, EDS-generated artifacts on the sample surface were at the time mistakenly attributed to irradiation-induced defects. Lessons learned from these studies will be presented and discussed in this talk. Modifications will be suggested providing an optimized experimental setup to avoid previous mistakes and to reduce impurities during implantation and measurements.
Proceedings Inclusion? Planned:
Keywords Ceramics, Characterization, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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