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Meeting MS&T24: Materials Science & Technology
Symposium Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
Presentation Title Emulation of Neutron Irradiation Induced Dislocation Loops, Elemental Segregation, and Precipitation Evolution at High Dose in 800H Using Dual Ion Beam
Author(s) Xingyu Liu, Xing Wang, Arthur T. Motta
On-Site Speaker (Planned) Xingyu Liu
Abstract Scope Accelerating the qualification of structural materials for advanced nuclear reactors is necessary for materials licensing at high doses. The 800H austenitic alloy spans both fast reactor and light-water reactor applications and can serve as a convenient benchmark for irradiation data. By characterizing the cavities, dislocation loops, elemental segregation, and precipitation induced by neutron irradiation, it is possible to understand the degradation of mechanical properties. Emulating the formation of these microstructural characteristics with dual ion irradiation (9MeV Fe and 3.42MeV He) makes it possible to compare the evolution of loops, elemental segregation, and precipitation at high doses (for now up to 81dpa). It was found that the faulted loop size-distribution can be emulated, and these loops can unfault to perfect loops through loop-loop interaction. However, the precipitation cannot be fully reproduced due to the much higher dissolution rate present in dual ion irradiation as compared to neutron irradiation.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

An Investigation of Post Heat-Treatment on the 316H Stainless Steel Fabricated by Laser Powder Bed Fusion
An Investigation of the Stability and Thermomechanical Properties of Binary Refractory Alloys Through Atomistic Simulations
Atomistic Insights into the Corrosion Behavior of NiCr Alloys in Molten FLiNaK Salt Using Reactive Force Field Molecular Dynamics
Atomistic Modeling of Irradiation-Induced Defects and Clusters in Additively-Manufactured Austenitic Stainless Steel
Characterization of In Situ and Ex Situ Ion Irradiated AM316L and AM316H Stainless Steels
Cold Spray and Friction Stir Processing Approach for Nuclear Applications: Manufacturing Mechanically and Thermally Stable Coatings
Degradational Effects of Single Crystal Deformation Mode and Corrosion Resistance due to Long-Range Order in Ni-Based Alloys for Nuclear Applications
Density Functional Theory Study of Helium diffusion in Ni-M Alloys (M= Cr, Mo)
Designing Heat/Corrosion Resistant Al-Cr-Fe-Ni-Ti Ferritic Superalloys
Development of Electron Beam Welding and PM-HIP Manufacturing of Advanced Reactor Pressure Vessels
Effect of Molten Halide Salts on Structural Alloy Creep at 650°-750°C
Embrittlement of Ni and Fe Based Alloys in Te- Containing Fluoride Salts
Emulation of Neutron Irradiation Induced Dislocation Loops, Elemental Segregation, and Precipitation Evolution at High Dose in 800H Using Dual Ion Beam
High-Throughput Exploration of Refractory High Entropy Alloys
High Temperature Mechanical and Irradiation Response of an Isostructural Refractory Eutectic Alloy
In-Situ Microstructural Evolution Under Extreme Environments
Innovative Processing and Characterization of Novel High-Strength and Corrosion-Resistant Cr/HEA Gradients for Fuel Cladding
Investigation of HIP Bonded AA6061 vs. AA6061 Cladding Interface as Functions of HIP Temperature and Cooling Rate
Performance Comparison of U-Net Based Machine Learning Architectures for Automated Analysis of TEM Images of Nuclear Materials
Radiation Performance of Doped High Entropy Alloys NiCoFeCr-3X (X=Pd/Al/Cu)
Stress Relief Optimization for Laser Powder Bed Fusion Printed 316H Stainless Steel
The Effect of Infinitesimal Potassium Doping on Incipient Plasticity and Ductile-to-Brittle Transition Temperature of Tungsten
Thermomechanical Fatigue Investigation of SS316L Fabricated via Laser Wire-Directed Energy Deposition
Understanding Corrosion Behavior of AA6061 Cladding Material Exposed to Nuclear Reactor Cooling Water Environments
What “Qualifies” as Nuclear-Grade Laser Powder Bed Fusion 316H Stainless Steel?

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