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About this Symposium
Meeting MS&T24: Materials Science & Technology
Symposium Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
Sponsorship TMS: Nuclear Materials Committee
TMS: Advanced Characterization, Testing, and Simulation Committee
Organizer(s) Miaomiao Jin, Pennsylvania State University
Xing Wang, Pennsylvania State University
Karim Ahmed, Texas A&M University
Jeremy Bischoff, Framatome
Adrien Couet, University of Wisconsin-Madison
Kevin Field, University of Michigan
Lingfeng He, North Carolina State University
Raul B. Rebak, GE Global Research
Scope Advanced nuclear reactor designs will play a critical role in meeting the ever-increasing demand for carbon-free energy worldwide. Compared to light water reactors (LWRs), the proposed advanced nuclear energy systems present an exceptionally harsh environment for the structural materials due to a combination of elevated temperature, increased radiation damage, extended service time, and more corrosive coolants. Furthermore, the growing interest in demonstrating advanced reactor designs requires the qualification process of structural materials to be accelerated. All these challenges must be tackled in order to realize the desired safety, efficiency, and economics of future nuclear reactors. Meanwhile, rapid progress in other emerging fields, such as additive manufacturing, high-throughput testing and simulation, multiscale modeling, and data analytics provide new avenues to addressing these challenges in structural materials for advanced reactors. This symposium aims to gather research on metallic structural materials, which can be the evaluation of existing material systems under new conditions or the design of advanced structural materials. Both experimental and computational work are welcome.

Abstracts are solicited in, but not limited to, the following areas:
• Novel structural material concepts for enhanced radiation tolerance
• New manufacturing processes (e.g., additive manufacturing)
• High-throughput testing and characterization of materials for nuclear applications
• Multiscale modeling and simulation
• High-throughput simulation and machine learning
• Corrosion in non-LWR and accidental conditions
• Microstructural evolution under extreme environments

Abstracts Due 05/15/2024
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

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 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
Investigating Corrosion of NiCr Alloys with Molten FLiNaK Salt Using ReaxFF Molecular Dynamics
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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