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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Synthesis and Irradiation Response of Hetero FeCr - Fe2O3 Interfaces
Author(s) Benjamin Kyle Derby, Jon Kevin Baldwin, Djamel Kaoumi, Danny Edwards, Daniel Schreiber, Timothy Lach, Blas Uberuaga, Nan Li
On-Site Speaker (Planned) Benjamin Kyle Derby
Abstract Scope Interfaces introduced in a structure act to influence the diffusion of solute atoms within that structure. In this work, a novel heterointerface between Fe8Cr and Fe2O3 is synthesized such that a network of misfit dislocations develops across the semi-coherent interface. This interface is synthesized by PVD sputtering a layered structure of a single-crystal, body-centered cubic Fe8Cr layer and a polycrystalline, rhombohedral Fe2O3 layer. This Fe8Cr-Fe2O3 thin film is then subjected to heavy Fe ion irradiation at 5.0 MeV and 250 oC. High-resolution electron microscopy is used to characterize the misfit dislocation network across the semi-coherent interface formed by the two materials with a misfit strain of 1.2 percent and to understand the material response under irradiation environments.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Thin Films and Interfaces, Characterization

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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
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