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Meeting MS&T22: Materials Science & Technology
Symposium Tackling Structural Materials Challenges for Advanced Nuclear Reactors
Presentation Title High-throughput Testing and Characterization of Materials For Nuclear Applications
Author(s) Michael Philip Short, Myles Stapelberg, Eleni Mowery, Elena Botica Artalejo, Gregory Wallace, Tonio Buonassisi, Isabel Alvarez
On-Site Speaker (Planned) Michael Philip Short
Abstract Scope Unlike progress in semiconductors, solar cells, or drug discovery, innovation in nuclear materials does not yet move at the speed of thought. We hypothesize that high-throughput workflow engineering centered around inference models between readily measurable properties and those of ultimate interest for nuclear structural materials (strength, ductility, toughness, thermal conductivity) can speed the pace of discovery, down-selection, development by a factor of 100. We employ a combination of thick-film physical vapor deposition or liquid-based combinatorial synthesis, followed by consolidation and microstructural optimization, and finally rapid measurements via in situ ion irradiation transient grating spectroscopy (I3TGS) and indentation plastometry during/between irradiations to correlate directly to fitness functions for each use case. We illustrate our ideas by tackling three systems: CuCr(Nb,Zr,Ti) alloys as RF antennas for plasma heating, plasma-facing first-wall high entropy alloys, and vanadium-based fusion structural materials, and will (hopefully) present our first results in this symposium.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Assessing Materials Susceptibility to Environmentally-assisted Cracking in Advanced Reactor Coolant Environments
Atomistic Calculations and Theoretical Formulations of Thermal Vacancies in Complex Concentrated Alloys
BCC CrAl Thin Film, A Solution for Next-generation High-performance Inert Gas Cooled Nuclear Microreactors
Computer Modeling of Oxidation-induced Grain Boundary Embrittlement in Nickel
Convolutional Neural Networks Screening Radiation-resistant High Entropy Alloys
Correlated Characterization of Ni-based Superalloys Corroded in Uranium-containing Molten Salt Systems
Defect Dynamics and Far-from-Equilibrium Microstructure Evolution in Concentrated Alloys
Deformation Behaviour of Ion-irradiated FeCr – A Nanoindentation Study
Electrochemical Determination Kinetic Properties of Ni2+ and Cr3+/Cr2+ in FLiNaK Molten Salt
Electrodeposition of Functionally Graded Interlayers for Enhanced Divertor/Heatsink Bonding for Fusion Reactors
Elucidating Interfacial Phenomena in Molten Salt Corroded Nickel-Chromium Alloys using Analytical Transmission Electron Microscopy
Heavy Ion Irradiation Response of an Additively Manufactured 316L Stainless Steel
Hierarchical Microstructures: A Potential Route to Enhanced Stability in Structural Materials for Advanced Nuclear Reactors
High-throughput Testing and Characterization of Materials For Nuclear Applications
High Temperature Zirconium Alloys by Titanium Analogy
ICME and ML Modeling Framework of U-10%wt Mo Fabrication Processes
Imaging Local Vacancy Supersaturation in Metals After Corrosion in Molten Salt
Impact of Chemical Short-range Order on Radiation Damage in Fe-Ni-Cr Alloys
In Situ Dual Ion Irradiation of Additively Manufactured Reduced Activation Ferritic-martensitic Steels
Interfacial Interactions between Molten Salt and Structural Materials
Investigation of Fracture Behavior of Nuclear Graphite NBG-18 Using In-situ Mechanical Testing Coupled with Micro-CT
Mechanical Behavior of Additively Manufactured Steels with Monotonic and Graded Microstructures
Mechanistic Calculation of the Effective Silver Diffusion Coefficient in Polycrystalline Silicon Carbide: Application to Silver Release in AGR-1 TRISO Particles
Microplasticity of Irradiated Inhomogeneous Alloys
Microstructural Evolution of High-throughput Additively Manufactured 316L Stainless Steel with Increasing Hafnium Dopants
Microstructural Response of HT-UPS Steel to Thermal Annealing and Neutron Irradiation
Microstructural Self-organization of Phase-separating Alloys during Irradiation into Global Compositional Patterns at Grain-Boundaries and Inside Grains
Multi-scale Modeling of the Mechanical Response of Structural Metals Subjected to Thermo-mechanical Loads and Irradiation: the Role of Microstructure.
Neutron Irradiation Effects in PM-HIP Nuclear Structural Alloys
Novel Refractory High Entropy Alloys for Applications in Extreme Environments
Phase-field Modeling of Radiation Induced Segregation for Multicomponent Alloys: Kinetic Monte Carlo and CALPHAD-Informed Simulations
Phase Field Modeling of Hot Isostatic Pressing for Joining of Dissimilar Metals
Progress Toward Additive Manufacturing of Ferritic-martensitic, In situ Tempered Steels for Nuclear Applications
Quantifying Cr and Fe Dissolution to Understand Stainless Steel Molten Salt Compatibility
Radiation Resistance of MAX and MAB Phase Materials
Structural Material Design for Power Plants Using Additive Manufacturing
Studying Microstructural Evolution in an Oxide Dispersion Strengthened 14YWT Ferritic Steel Tube Manufactured using SolidStirTM Technology
Synchrotron High-energy X-ray Studies of Nuclear Structural Materials
Understanding of Alloying Additions for Design of Gas Atomization Reaction Synthesis Produced Oxide Dispersoid Strengthened Alloys

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