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Meeting MS&T24: Materials Science & Technology
Symposium Tackling Metallic Structural Materials Challenges for Advanced Nuclear Reactors
Presentation Title Innovative Processing and Characterization of Novel High-Strength and Corrosion-Resistant Cr/HEA Gradients for Fuel Cladding
Author(s) Mohan Sai Kiran Kumar Yadav Nartu, Daniel Yoon, Subhashish Meher, Mageshwari Komarasamy, Lei Li, Ayoub Soulami, Isabella Van Rooyen
On-Site Speaker (Planned) Mohan Sai Kiran Kumar Yadav Nartu
Abstract Scope The strength and corrosion resistance of the fuel cladding is critical to prevent corrosion of fuel rods by the coolant and the release of fission products into the coolant. High entropy alloys(HEAs) have recently gained traction due to their excellent mechanical and irradiation properties. In this work, we investigate a novel gradient (Cr->HEA) alloy for fuel cladding where the gradient advances from pure-Cr to HEA(CoCrFeNiCu0.12) radially inwards. Unlike axial gradients, which are easy to fabricate via multiple processing methods, radial gradients are challenging to manufacture, and barely any literature has depicted their success. In this study, we have designed an innovative processing methodology using the Hot Iso-static Process(HIP) to fabricate Cr-HEA radial gradients. The gradient compositions were designed using Thermo-Calc to avoid the brittle sigma phase during fabrication, and HIP-process parameters were developed to achieve complete densification. This presentation will also discuss the microstructural characterization and performance of the gradient-HEA.

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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