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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Novel Fiber Fretting Technique for Tribological Properties of Composite Interphases
Author(s) Joseph R. Kabel, Thomas E. J. Edwards, Caroline Hain, Tatiana Kochetkova, Johann Michler, Peter Hosemann
On-Site Speaker (Planned) Joseph R. Kabel
Abstract Scope Ceramic matrix composites exhibit excellent high temperature properties and are candidate materials for application as nuclear fuel cladding. The strength and deformation behavior of these composites are intrinsically tied to the properties of the fiber/matrix interphase. This research introduces a novel technique to evaluate the fundamental friction and wear characteristics of these interfaces. A case study on SiCf/PyC/SiCm composites applies in situ fiber fretting to investigate the kinetic friction coefficient (μk) and cyclic wear characteristics. Testing was carried out as a function of fiber type, PyC thickness (≈10, 500, 1200nm), cycle count (10, 100, 1000), and frequency (1, 5, and 10 Hz). The friction coefficient and behavior changed with cycle length as it related to transition from adhesive to abrasive friction mechanisms. SEM fractography provided insights to tribological evolution from adhesive sliding to three-body abrasive wear. The surface structural disorder contribution to adhesive resistance was investigated using Raman spectroscopy.
Proceedings Inclusion? Planned:
Keywords Composites, Mechanical Properties, Thin Films and Interfaces

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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