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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 Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Author(s) Alexander Leide
On-Site Speaker (Planned) Alexander Leide
Abstract Scope The drawbacks of ion irradiations to replace neutron irradiations are generally well acknowledged, and methods have been developed to account for dose rate or characterising small volumes of material. Radiation defect induced swelling is an important phenomenon which has generally been neglected in post irradiation characterisation of ion irradiated materials. Ion irradiated layers are thin films constrained by a substrate, therefore swelling is anisotropic and causes residual stresses between the substrate and thin film. These stresses can cause defects to evolve differently due to creep, potentially resulting in different radiation defects, and different measured micromechanical results. Examples of the effects of swelling stress on micromechanical and spectroscopic measurements will be shown, along with residual stress measurements on ion irradiated materials, and potential effects on lift-out characterisation techniques such as TEM will be discussed. The potential for exploiting or controlling radiation-induced residual stresses in engineering components beneficially will be discussed.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials, Ceramics

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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