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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 Small Scale Tests, Big Lessons Learned
Author(s) Eric Lang, Brad Boyce, Khalid Hattar
On-Site Speaker (Planned) Eric Lang
Abstract Scope Nanomechanical tests have become impactful nuclear materials methods. When done correctly, they offer information on the mechanisms of material deformation and failure. However, numerous trials and errors go in to determining the correct size, shape, and test parameters to generate effective data. This talk will highlight the lessons learned in a series of small-scale mechanical tests, from ion irradiated micropillar compression to size-dependent cantilever fracture to specimen shaping effects. It demonstrates the importance of correlating plastic zones and irradiation damage in compression, considering the specimen dimensions for appropriate tests, and issues around repeatability of nanoscale experimentation. Through a decade of insights from learning from failures, this talk will present recipes for success, or well, avoiding similar pitfalls. This work was partially supported DOE Fusion Energy Sciences.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Mechanical Properties

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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