ProgramMaster Logo
Conference Tools for MS&T24: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting MS&T24: Materials Science & Technology
Symposium Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
Presentation Title L-7: Cold Spray and Friction Stir Processing Approach for Nuclear Applications: Manufacturing Mechanically and Thermally Stable Coatings
Author(s) Syed Rizvi, Md Jasim Uddin, Aniruddha Malakar, Robert McRobie, Florian Laggner, Bharat Gwalani, Elizabeth Kautz
On-Site Speaker (Planned) Syed Rizvi
Abstract Scope AA6061 is a precipitation-hardened alloy that has found broad applications in research reactors due to its excellent mechanical properties, formability, and good corrosion resistance. It is most widely used in fuel manufacturing, cooling pipes, and framing of nuclear structures. Nuclear fuel pallets are formed using a technique where they are sandwiched between several layers of AA6061 and further enclosed in AA6061-T6. Surface of AA6061 is prone degradation via cacking, abrasion and corrosion. Here, we have modified the surface of AA6061-T6 using Al+Al2O3 via cold spray (CS) followed by friction stir processing (FSP). The effects of FSP on microstructure and mechanical properties as function of temperature will be presented, and avenues for adoption by the nuclear industry will be discussed.

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
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)
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
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
L-7: Cold Spray and Friction Stir Processing Approach for Nuclear Applications: Manufacturing Mechanically and Thermally Stable Coatings
L-8: Designing Heat/Corrosion Resistant Al-Cr-Fe-Ni-Ti Ferritic Superalloys
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?

Questions about ProgramMaster? Contact programming@programmaster.org