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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 Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Author(s) Mackenzie Warwick, Wyatt Peterson, Ben Arms, Charles Hirst, Kevin Field
On-Site Speaker (Planned) Mackenzie Warwick
Abstract Scope Ion-irradiation-thin stress-gradient tensile specimens were developed for accelerated creep testing. The effect of this stress gradient on the multi-length-scale microstructural evolution in 316SS was investigated under thermal and proton irradiation creep conditions. A series of experiments (79-158 MPa, 158-316 MPa) at (400℃, 550℃) were performed to 0 and 0.2 dpa over 150 hours. Initial characterization of the irradiated microstructures shows preferential alignment of dislocation lines and loops suggesting stress-induced preferential absorption mechanisms, cellular dislocation network formation and evolution, and formation of Ni3Si clusters along dislocation lines. The observation of small (<15 nm) loops and defect clusters from irradiation suggests there are previously unevaluated microstructure length-scale interactions, particularly how these small clusters contribute to pinning of mobile dislocations. These preliminary results demonstrate the value of performing stress-gradient experiments to probe the microstructural and microchemical behavior during irradiation creep for informing engineering component designs in nuclear energy systems.
Proceedings Inclusion? Planned:
Keywords Characterization, Nuclear Materials, 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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