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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Competition between Void Evolution and Amorphization In Radiation-tolerant Nanocrystalline Cu-10at%Ta Alloy
Author(s) Priyam Patki, Wei-Ying Chen, Janelle P Wharry
On-Site Speaker (Planned) Priyam Patki
Abstract Scope The objective of this study is to understand the role of cascade morphology on the ion irradiation evolution of nanostructured Cu-10at%Ta alloy. The alloy is immiscible and has nanocrystalline Cu grains with a bimodal distribution of Ta nanoparticles. In this study, TEM in situ irradiation is conducted on Cu-10at%Ta lamellae using Ne, Kr, and Xe ions at temperatures ranging 100-400℃ to doses up to 10 displacements per atom (dpa). Irradiation-induced voids are observed at higher temperatures. Void onset dose decreases with cascade size, but void number density increases for smaller cascades. Irradiation-induced core-shell amorphization of Ta particles occurs at lower temperatures and with larger cascades. Amorphization and void formation compete at moderate temperatures. The point defect balance equations can explain these results by ascribing voids to the vacancy flux, and amorphization to the interstitial flux. This work provides insight into irradiation disordering of nanoparticles in oxide dispersion strengthened (ODS) alloys.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Nanotechnology, Characterization

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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