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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications II
Presentation Title An Innovative Additive Manufacturing Route for Metal Matrix Composites for Nuclear Applications
Author(s) Taegyu Lee, Wonjong Jeong, SeunhHyeok Chung, Ho Jin Ryu
On-Site Speaker (Planned) Ho Jin Ryu
Abstract Scope As metal additive manufacturing has been actively applied in many industries, much research has focused on the development of additive manufacturing for nuclear applications. However, the additive manufacturing of metal matrix composites for nuclear applications is still in the emerging stage because printable raw materials are not sufficient and the solidification of reinforcement-bearing metals during the additive manufacturing processes has not been fully established. In this study, the progress of additive manufacturing of various metal matrix composites by using a newly proposed surface modification and reinforcement transplantation technology is introduced. The manufactured metal matrix composites include Y2O3 dispersed alloys for radiation resistance, B4C dispersed Al composites for neutron shielding, and TiC dispersed Ni-base superalloy for high-temperature applications. Both the strengthening of the reinforcements and better solidification behavior improve the mechanical properties of the additive manufactured metal matrix composites, which is beneficial for structural and functional applications under extreme conditions.
Proceedings Inclusion? Planned:
Keywords Additive Manufacturing, Composites, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

An Innovative Additive Manufacturing Route for Metal Matrix Composites for Nuclear Applications
Characterization of Defects Generated from Thermal Stresses in SiC/SiC Composites
Characterization of the Effects of Intermediate Temperature Neutron Irradiation on Model Fe-Cr Alloys
Correlating Heterogeneous Pore Distribution with Stochastic Fracture in the Pyrocarbon Buffer Layer in TRISO Fuel Particles
Development and Additive Manufacturing of ODS IN-718 Alloys for Nuclear Applications
Development and Evaluation of Dual-purpose Coating to SiC/SiC Composite Accident-tolerant Fuel Cladding for Light Water Reactors
Development of SiCf/SiC Composite Materials for Fusion Applications
Effect of Copper Fiber in RAFM Steel Composite on Improving the Thermal Conductivity
Effect of Hot Rolling and High Temperature Annealing on the Microstructure and Mechanical Properties of Hot-rolled 90W7Ni3Fe WHA
Effect of Interfacial Features on the Strengthening Behavior of B4C/Al Composites
ENHANCED Shield: A Critical Materials Technology Enabling Compact Superconducting Tokamaks
Ion Beam Synthesis of Nano-Oxides in FeCr: Towards an Understanding of Precipitation in Oxide Dispersion Strengthened Steels
Irradiation Effects in the Composite Phases of Graphite and Carbon-Based Materials
Is there Residual Stress in Tungsten Fiber Reinforced Tungsten Composites
Mechanistic Understanding of Hydrothermal Corrosion of SiC Under Irradiation
Microstructure and Mechanical Behavior of Cr Coatings for Mitigating Hydrothermal Corrosion of SiC-SiCf Fuel Cladding
Microstructure and Thermophysical Property Characterization of U-ZrHx Fuel Fabricated by Powder Metallurgy
Next-generation Nuclear Grade Composite Components
Nuclear Graphite as a Core Composite Material
Oxidation Effects on the Microstructure of Nuclear Graphite
Oxidation Response of Irradiated and Unirradiated TRISO Fuel
Progress in the Development of Tungsten Fibre-reinforced Copper Composites for Heat Sink Applications in Plasma-facing Components
Recent Progress in the Development of Tungsten Fibre-reinforced Tungsten Composite
Role and Structure of HTGR Matrix Material
Ruthenium and Silver Diffusion in Nuclear Graphite
Status Update on Framatome PROtect ATF Solutions: Cr-coated M5Framatome and SiCf/SiC Cladding Designs
Stress Rupture of SiC/SiC Composite Tubes Under High-temperature Steam: Implications for Resistance to Light Water Reactor Accident
Thermal Properties of Dispersoid-strengthened Tungsten Alloys for Fusion Applications
W2C-reinforced Tungsten: A Promising Candidate for EU DEMO Divertor Material

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