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 Development of Electron Beam Welding and PM-HIP Manufacturing of Advanced Reactor Pressure Vessels
Author(s) Janelle P. Wharry, Elliot Marrero Jackson, Grayson A Nemets, Jasmyne Emerson, Yu Lu, Maria A Okuniewski, Benjamin Sutton, David W Gandy
On-Site Speaker (Planned) Janelle P. Wharry
Abstract Scope This talk will present the current status toward nuclear code-qualification of reactor pressure vessel (RPV) steels fabricated by powder metallurgy with hot isostatic pressing (PM-HIP), and electron beam (EB) welds of these steels. The combination of PM-HIP and EB welding offers the potential to significantly reduce RPV construction time and cost, propelling new nuclear construction. But qualification of these materials in the ASME Boiler & Pressure Vessel Code, and eventual regulatory acceptance, requires their evaluation in relevant irradiation environments. We will discuss two neutron irradiation campaigns that evaluate the microstructural and mechanical evolution of PM-HIP and EB welded PM-HIP SA508 Grade 3 Class 1 steel, compared to an SA508 forging. Differences in irradiation hardening and embrittlement between the PM-HIP and forging will be discussed in the context of the irradiated microstructure. Recommendations for post-EB weld heat treatments and next steps toward material qualification 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