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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Opportunities for Nanostructured Tungsten Alloys in Composite Fusion Materials
Author(s) Jason Trelewicz, Nicholas C. Olynik, Wenbo Wang, David J. Sprouster, Chad M. Parish
On-Site Speaker (Planned) Jason Trelewicz
Abstract Scope Tungsten has emerged as the primary armor material for plasma facing components (PFCs) due to its attractive properties, resistance to sputtering, and chemical compatibility with tritium. Recognizing that embrittlement and thermal conductivity degradation from neutron loading are potentially insurmountable issues for tungsten, advanced tungsten-based alloys and composites are being explored as engineered materials for PFCs. However, in tungsten/tungsten composites, the matrix will still inherently be limited by the same issues plaguing bulk tungsten. In this presentation, we discuss opportunities for nanostructured tungsten alloys designed specifically for the fusion environment as a stable matrix phase of tungsten-based composites. Guided by thermodynamic models of dopant distributions, a ternary system is identified for enhancing stability and manufacturability. Alloys are synthesized via powder metallurgical processing and analyzed using synchrotron x-ray diffraction and small angle x-ray scattering experiments. The benefits of microstructures containing desirable nanoscale compositional heterogeneities are finally discussed for nanostructured tungsten-based composite PFCs.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, High-Temperature Materials, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Novel Processing Route for ODS Steel by Liquid Metallurgy
Competition between Void Evolution and Amorphization In Radiation-tolerant Nanocrystalline Cu-10at%Ta Alloy
Conformal Tungsten Coatings for Cermet Nuclear Fuel Elements
Corrosion and TEM Analysis of CVD and PVD Coatings for BWR Accident Tolerant Fuel Cladding
Coupled Primary and Secondary Recrystallization in Single Tungsten Fiber-reinforced Tungsten Composites
Development of PVD Cr Coatings for Hydrothermal Corrosion Mitigation of SiC-SiCf Fuel Cladding in LWRs
Development of UN/UO2 Composite Fuels for LWR Applications
Enhanced Microstructural Stability of ARB-processed Cu/Nb Nanolayers Under Heavy Dose Ion Irradiation at Elevated Temperatures
Evaluation and Irradiation of 14YWT Capacitive Discharge Resistance Welds
Experimental Characterisation of the Variation of Local Residual Stresses in TRISO Coatings
Fabrication, Characterisation and Oxidation Resistance of an Innovative Composite Fuel: UN Microspheres Embedded in UO2 Matrix
Improved Techniques for Determining Local Thermal Transport in Composite Nuclear Fuels
Irradiation Induced Forced Chemical Mixing and Local Hardening in Mechanically-processed Immiscible Zr/Nb Multilayers
Mechanical Strength of Explosion Welded Thin Stainless-steel Cladding on Carbon Steel
Novel Fiber Fretting Technique for Tribological Properties of Composite Interphases
Opportunities for Nanostructured Tungsten Alloys in Composite Fusion Materials
Overview of the Westinghouse Accident Tolerant and High Burnup Fuel Program
Post-irradiation Examinations of TRISO Particles Corroded in Molten FLiBe Salt under Neutron Irradiation
Radiation Tolerance and Microstructural Changes of Nanocrystalline Cu-Ta Alloy to High Dose Self-ion Irradiation
SiGA SiC-SiC Composites Development for Accident Tolerant Fuel
Solving the Brittleness Problem of Tungsten - Tungsten Fibre-reinforced Tungsten Composites
Sub-critical Crack Initiation, Coalescence and Propagation in Nuclear Graphite Studied by High-speed Pink Beam Synchrotron Tomography
Synthesis and Irradiation Response of Hetero FeCr - Fe2O3 Interfaces
Tristructural Isotropic (TRISO) Fuel for High-Temperature, Passively-Safe Nuclear Reactors
Tungsten-based High and Medium Entropy Alloys and Composites for Nuclear Applications
Tungsten Fibre-reinforced Copper – A High-Conductivity, High-Strength Composite Material for Plasma-facing Component Applications
Understanding Defect Recovery and Accommodation and Their Implications on Mechanical Performance in Irradiated Nanocomposite Materials
Uranium Nitride Advanced Fuel: An Evaluation of the Oxidation Resistance of Coated and Doped Grains
Use of Carbon Fibre-reinforced Carbon in Wendelstein 7-X
W2C-reinforced Tungsten: A Promising Candidate for DEMO Divertor Material

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