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Meeting MS&T23: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments IV
Presentation Title Interdiffusion Behaviour of UN with Zircaloy-4 via Diffusion Couple Studies
Author(s) Max Salata-Barnett, James Buckley, James Paul, Dave Goddard, Tim Abram
On-Site Speaker (Planned) Max Salata-Barnett
Abstract Scope Uranium nitride (UN) has been of particular focus recently as an advanced fuel candidate for light water reactors (LWRs) having both a high uranium density and thermal conductivity. The interaction between UN and zirconium alloys has not been studied in great detail. To assess fuel-clad suitability, diffusion couples between UN and zircalloy-4 have been performed up to 1000C for durations up to 100 hours. Minimal interaction was observed at low temperatures (400C). At temperatures of 700C and above, interaction was observed resulting in bonding of the UN and Zircalloy-4. Investigation via electron microscopy has revealed significant migration of uranium into the Zircalloy-4, up to depths of 500 m within the 100 hour experiments. In addition to the movement of uranium, other elements within the fuel-clad combination also undergo relocation and form additional phases at the contact interface. This study applies modern techniques to enhance the limited data available.


Accelerated Assessment of Microstructure-Mechanical Property Relationships in Ni Based Superalloys
Accelerated Creep Testing for High-Temperature and Nuclear Applications
Advanced In-situ Strain Mapping for Zr Oxidation by 4D-STEM
Assessing the Ability of Nuclear Fuel Performance Codes to Predict Radially Resolved Properties in Oxide Fuels
Capturing 3D Evolution of Twin Networks in Titanium as a Function of Applied Strain
Effect of Solutes on the Radiation Induced Segregation in Ferritic Alloys at ∑3- grain Boundaries
Effect of Strain Rate on Tensile Properties of C250 Maraging Steel
Enabling Multiscale Materials Characterization with Machine Learning
Four-dimensional Scanning Transmission Electron Microscopy (4D-STEM) Characterization of Intergranular Corrosion of Austenitic Stainless Steels in Lead-bismuth Eutectic
High-Temperature Irradiation Behavior of Piezoelectric Aluminum Nitride
In Situ SEM Nanomechanics at Cryogenic Temperatures
Interdiffusion Behaviour of UN with Zircaloy-4 via Diffusion Couple Studies
M-1: Novel Method for Fabricating and Analysis of 3D Printed Composite for Radiation Shielding Containing Metalized Halloysite Nanotube
Mapping Elemental Distributions Across Thin Corrosion Films Formed on Nuclear Reactor Core and Structural Materials via Ex-situ And In-situ Atom Probe Tomography
Multimodal Characterization of Materials Corrosion in Molten Salts
Phase Stability of Delta-ZrH Under Ion Irradiation
Probing Nanoscale Properties of Radioactive Material by Advanced Correlative Microscopy
STEM-based Mapping of Nanoscale Point Defects Produced via Temperature, Irradiation, And Corrosion
Structural Stability of REE-PO4 (REE=Sm,Tb) under Swift Heavy Ion Irradiation
Thermodynamic Modeling and Calculation of Phase Formation Processes Under Irradiation Conditions of Uranium-plutonium Nitride Fuel
Transition Metal Carbonitride Materials Exposed to Swift Heavy Ions

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