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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications II
Presentation Title Effect of Copper Fiber in RAFM Steel Composite on Improving the Thermal Conductivity
Author(s) Yong Hwan Cho, Hyun Joon Yang, Chang-Hoon Lee, Woong-Ryeol Yu, Heung Nam Han
On-Site Speaker (Planned) Yong Hwan Cho
Abstract Scope Reduced activation ferritic/martensitic (RAFM) steel is one of the primary candidates for blanket modules in a nuclear fusion reactor. Increasing the thermal conductivity of the blanket material contributes to improve the efficiency of the fusion reactor. This study aimed to fabricate composite materials that have higher thermal conductivity than conventional RAFM steel by adding copper fibers in the steel. To compare the effect of fiber types on the thermal conductivity, copper powder and 3D woven copper mesh were used. The composite materials were fabricated by utilizing spark plasma sintering. To calculate the thermal conductivity of the specimens, their thermal diffusivity and heat capacity were measured by using laser flash apparatus and differential scanning calorimetry. The mechanical properties were also measured by miniature tensile test. 3D copper mesh can effectively improve the thermal conductivity of the composites, but the optimization between their thermal and mechanical properties should be conducted.
Proceedings Inclusion? Planned:
Keywords 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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