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Meeting MS&T24: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
Presentation Title Real-time Neutron Diffraction to Support Interpretation of DSC Results on Zr-2.5Nb for Reactor Pressure Tubes
Author(s) Sven C. Vogel, Amy I. Fluke, Daniel J. Savage, Toshiro Tomida
On-Site Speaker (Planned) Sven C. Vogel
Abstract Scope Under postulated accident scenarios dual-phase Zr-Nb cladding or pressure tube material with α (hcp) and β (bcc) phases may be subjected to high temperature transients up to 1200°C, resulting in heating rate-dependent α-β phase transformation. Since the thermophysical properties are affected by the phase changes, it is important to understand this behavior in order to predict the performance under extreme thermal transient conditions. A hysteresis in calorimetry measurements was observed between heating and cooling. Furthermore, as-manufactured tube material showed a small enthalpy change during first heating that did not appear on subsequent heating. Neutron diffraction with an identical temperature profile (heating rate of 20C/min) was performed on the HIPPO diffractometer to understand these observations. Phase fractions, lattice parameters and texture evolution were tracked with a 15 second time resolution for comparison with previous DSC data and modelling of phase transformation textures using the Double-Burgers orientation relationship method.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization Capabilities of Nuclear Materials via NSUF
Advanced In-Situ Strain Mapping for Zr Oxidation by 4D-SPED
An In-Situ Transmission Electron Microscopy Study on the Synergistic Effects of Heating and Biasing of AlGaN/GaN High Electron Mobility Transistors
Application of Laboratory-Based Photoelectron Spectroscopy with Hard and Soft X-Rays to Nuclear Forensics Characterization of Uranium Dioxide Fuel
Atomic-Scale Hidden Point-Defect Complexes Induce Ultrahigh Irradiation Hardening in BCC Metals
Characterization of Aluminum Under Shock: Defects, Grain Orientation, and Phase Stability
Characterization of Radiation Damage in Nanocrystalline Ni- and Fe-Based Oxide Dispersion-Strengthened Alloys
Deciphering and Visualizing Helium Accumulation and Dynamics in Materials via In-Situ Characterization
Deployment and Testing of a Fiber-Based Instrument for In-Reactor Thermal Property Measurements at MIT Research Reactor
Determination of Molten Salt Thermal Conductivity Using Laser Flash Technique
Dynamics of Radiation Defect Accumulation in Non-Metallic Materials
Effect of Swift Heavy Ion Irradiation on Silicon Carbide
Formation and Recover of Dislocations Under Deformation and/or Irradiation of Elemental Tantalum, a Step Toward Understanding Complex BCC Alloys.
Impact of Amorphous Pockets on Displacement Damage Evolution in Crystalline Silicon
Influence of Defects Length-scale on Nuclear Graphite Properties
Interactions Between Radiation-Induced Defects and Shock in Al 1100
Investigation of Helium Bubble Formation at Tungsten-Dispersoid Interfaces in Dispersion-Strengthened Tungsten Alloys
Localized Crystallization of Zr Following Heavy Ion Irradiation of HfNbTaZr MPEA
Machine Learning and Molecular Dynamics-Coupled X-Ray Absorption Spectroscopy for Disordered Multicomponent Systems
Microstructural and Chemical Evolution Studies of U-10Zr Metallic Fuel and HT9 Cladding from Fast Flux Test Facility
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Nanoscale Redistribution of Lithium in Neutron Irradiated LiAlO2
Neutron-Induced Reversible Nanostructuring of GeSe2
Quantitative Phase Characterization of Nuclear Cements and Concretes Using Non-Destructive 3D Automated Mineralogy and Enhanced Deep-Learning Reconstruction via X-ray Microscopy
Real-time Neutron Diffraction to Support Interpretation of DSC Results on Zr-2.5Nb for Reactor Pressure Tubes
Strong Dependence of 2D Material Radiation Tolerance on the Composition of the 2D Material and Its Surrounding Environment
Structural Characterization of Ultra-High Temperature Ceramics in Three Dimensions for Statistical and Physics-Based Modeling
Superimposed Effects of Texture and Grain Shape Anisotropy on Biaxial Creep Behavior of Nb-Modified Zircaloy-4 Cladding
Surface Microstructure Evolution and Associated High Temperature Anti-Oxidation Mechanisms of Copper with Vapor Deposited Graphene
Synthesis and Irradiation of Uranium Carbide and Nitride for TRISO Development
Thermophysical Characterisation of Zirconium-Based Nuclear Materials
Thermophysical Properties of Irradiated Yttrium Hydride Moderator Material
Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Understanding Irradiation Assisted Hydrogen Embrittlement Using In Situ Coherent X-Ray Imaging
Understanding the Mechanism of Fission Gas Re-Solution and Blistering in UMo Fuel via Atomistic Modelling
Understanding the Surface and Near Surface via Nanomechanical Mapping

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