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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications
Presentation Title A Superb Void Swelling Resistant Type 316L Stainless Steel Developed by Additive Manufacturing Enabled High Throughput Microalloying
Author(s) Miao Song, Jingfan Yang, Xiang Liu, Xiaoyuan Lou, Yongfeng Zhang, Lingfeng He, Daniel Schwen
On-Site Speaker (Planned) Miao Song
Abstract Scope Additive manufacturing (AM) has drawn increasing attention in the nuclear industry. However, data are still limited relevant to radiation damage in AM alloys. Previous results indicate that the void swelling resistance of AM 316L stainless steel (SS) was inferior compared to hot-isotropic pressing counterparts in high-temperature self-ion irradiation. Here, we show that the swelling resistance of AM alloys can be significantly improved by microalloying. Gradient 316L SS with 5 different Hf concentrations was printed in a small volume and then irradiated with 5 MeV Fe2+ ions under identical conditions to 50 dpa at 500-600℃. Void swelling decreases monotonously as the concentration of Hf increases to 1 wt.% at all three temperatures. With 1wt.% Hf, the void swelling of microalloyed AM 316L was one-two orders of magnitude lower compared to undoped AM 316L. This investigation demonstrates that the AM enabled high throughput microalloying is promising for nuclear materials development.
Proceedings Inclusion? Planned:

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Rapid Turnaround Approach Studying Helium Effects in Materials
A Standards Perspective on Nanomechanical Testing to Accelerate Nuclear Materials Development & Qualification
A Superb Void Swelling Resistant Type 316L Stainless Steel Developed by Additive Manufacturing Enabled High Throughput Microalloying
Accelerated Study of Thermal and Irradiation Creep in Fe-based Multi-principal Element Alloys
An Integrated Approach for Coupling Experimental Data, Physics-based Models, and Machine Learning Algorithms for Predicting the Effective Thermal Conductivity of U-based Fuels
Anisotropic Biaxial Creep Behavior of Textured Nb-modified Zircaloy Cladding
Characterization of As-Fabricated Additively Manufactured Alloy 718 Enhanced by Modern Tools and Machine Learning
Comparison of Void Swelling in Conventional and Novel HT9 Alloys after High Damage Level Ion Irradiation
Compositionally Graded Bulk Specimen: A High-throughput Approach for Nuclear Alloy Development and Qualification
Constructing Multi-component Diffusion under Irradiation in U-Mo Alloys
Deep Learning for Automated Analysis of Cavities in Transmission Electron Microscopy Images
Defect Cluster Mobilities and Preferred Configurations in α-zirconium: A Comparison of Two Interatomic Potentials
Development and Qualification of Ultrafine-grained and Nanocrystalline Steels for Nuclear Applications
Development of Assembly Technique for Fuel Specimens for the MARCH-SERTTA TREAT Irradiation Testing Platform
Development of Sintered High Strength and Thermal Conductivity Cu-Cr-Nb-Zr Alloy for Fusion Components
Dislocation Loop Characterization Using STEM-Contrast Techniques in an Irradiated FCC Alloy
Dislocation Loop Formation in Self-ion Irradiated Ultra-high Purity FeCr Alloys
Effect of Distributed Gas Bubbles on Elastic-plastic Deformation Behavior in Polycrystalline UMo
Effect of Microstructure and Rolling Treatment on Static Recrystallization Behavior in Monolithic U-10Mo Fuel Foils
Effective Bias for Interstitial Clusters to Cavities in BCC Fe
Evaluation of Creep Deformation of Ferritic/Martensitic (FM) Grade 91 Steel Fabricated Using Wire Arc Additive Manufacturing (WAAM)
Helium Effect on Cavity Swelling in Dual-ion Irradiated Fe and Fe-Cr Alloys
High-temperature, High-throughput Ion Irradiation Enabled by Additive Technologies
High-throughput Heavy Ion Irradiation of CrFeMnNi Magnetron-sputtered Combinatorial Thin Film
High power irradiation testing of TRISO MiniFuel-Compacts in HFIR
Improving Irradiation Resistance of Alloys by Controlling Defect Diffusion: A Modeling Perspective
In-situ TEM Heating Chip Experiments to Study Thermal Behavior of U-Zr Metallic Fuel
In-situ Thermal Conductivity Measurement of SiC Composite
Machine Learning and Atomistic Modeling of Defect Diffusion in Concentrated Ni-Fe Alloys
Machine Learning for Accelerating Property Prediction and Materials Characterization in Irradiated Materials
Machine Learning Perovskites in the Quest for Improved Scintillators
Manufacturing Process Optimization of High-density LEU Targets for Mo-99 Production
Materials Selection in Nuclear Applications a Challenge and an Opportunity for Advanced Material Design, Fabrication and Testing
Mesoscale Modeling of the Effect of Interfaces on Segregation of Point Defects and Solutes and the Patterning of Extended Defects
Microscale Measurement of Elastic Constants in Ceramics Using Picosecond Ultrasonics for High Throughput Characterization and Atomic Model Validations
Modeling and Analysis of the Effects of the Microstructure on U-10Mo Fuel Thickness Variation during Hot Rolling
Molecular Dynamics Study of Cascade Overlap Effects in FCC Ni
Multiscale Characterization of Defects in Ion Irradiated Ceramics for Validation of Atomistic Models
Overview of Advanced Fuels and Materials R&D within the US DOE-NE NEAMS Program
Overview of Nuclear Materials Discovery and Qualification Initiative (NMDQi)
Point Defect Capture Characteristics and Stress States of Dislocation Loops in α-zirconium
Point Defect Energies in Concentrated Alloys Using Ab Initio Calculations and Machine Learning
Properties of a Helium Ion Beam Degrader for Implanting SSJ2 Tensile Specimens at the LBL 88-Inch Cyclotron
Proton Irradiation Induced Microstructural Evolution in Compositionally Graded Type 316L Stainless Steel
Qualification of 316L Stainless Steel Components for ASME Pressure Retaining Applications
Role of Composition and Thermal Aging on Corrosion Behavior of Duplex Stainless Steels in Pressurized Water Reactors
Sink Strength Effect on Bubble Formation in Helium-implanted Nanostructured Ferritic Alloys
Synergistic Irradiation and Ageing Effect on Microstructure and Mechanical Properties of Grade 92 at ~700C

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