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Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications II
Presentation Title W2C-reinforced Tungsten: A Promising Candidate for EU DEMO Divertor Material
Author(s) Petra Jenus, Aljaž Iveković, Matej Kocen, Anže Abram, Andreja Šestan Zavašnik, Sabina Markelj, Andrei Galatanu , Magdalena Galatanu , Elena Tejado, Jose Ygnacio Pastor, Marius Wirtz, Saša Novak, Gerald Pintsuk
On-Site Speaker (Planned) Aljaž Iveković
Abstract Scope Tungsten is considered as the material of choice for the divertor application of fusion power plants due to its intrinsic thermo-physical properties. One main drawback is the recrystallization induced reduction of its mechanical properties at elevated temperatures. The aim of this research was to improve the material properties to be able to sustain plasma-facing conditions, especially to be able to resist high thermal loads imposed on the divertor during operation. The reinforcement of tungsten by incorporation of carbide nanoparticles, resulted in a material with a stable microstructure and promising behaviour. WC nanoparticles were used as a source for the in-situ formation of W2C inclusions in the W matrix during the thermal treatment of powder mixtures with a field assisted sintering technique. This work has been carried out within the framework of the EUROfusion Consortium No633053. The projects ARRS: P2-0087-2, P2-0405-5 and J2-8165 and MAT2015-70780-C4-4-P and S2013/MIT-2862-MULTIMATCHALLENGE are acknowledged.
Proceedings Inclusion? Planned:
Keywords High-Temperature Materials, Nuclear Materials, Process Technology

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
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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
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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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