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Meeting 2015 TMS Annual Meeting & Exhibition
Symposium Characterization of Nuclear Reactor Materials and Fuels with Neutron and Synchrotron Radiation
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
Organizer(s) Jonathan Almer, Argonne National Laboratory
Meimei Li, Argonne National Laboratory
Donald Brown, Los Alamos National Laboratory
Tiangan Lian, Electric Power Research Institute
Scope Neutron and synchrotron radiation sources offer new opportunities to advance the fundamental understanding of nuclear reactor materials, fuels and engineering components. A variety of advanced characterization tools including diffraction, imaging and spectroscopy have recently become available to allow measurements of microstructure and strain over a range of relevant time and length scales, on both pre- and post-irradiated materials, and under in situ conditions including stress and temperature. The symposium will highlight recent experimental efforts and future prospects to characterize material and fuel systems for nuclear reactor application using neutron and synchrotron radiation techniques, including possibilities for in-situ irradiation. Areas covered will include stress/strain mapping, void and crack initiation and propagation, phase stability and phase transformations, characterization of irradiation defects and nanoclusters, and corrosion.
Abstracts Due 07/15/2014
Proceedings Plan Planned: A print-only volume
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

Atomistic Modeling and Diffraction Analysis of Metallic Uranium Alloys
Characterization of Grain Growth in Nano-Grained UO2 with In Situ High Energy X-ray Diffraction and TEM
Characterization of Ion Beam Irradiated 304 Stainless Steel Utilizing Nanoindentation and Laue Microdiffraction
Characterization of Nano-Precipitates in Irradiated RPV Steels: A Critical Comparison of SANS and APT Techniques
Characterization of Neutron-Irradiated HT-UPS Steel by High-Energy X-ray Diffraction Microscopy
Characterization of Swift Heavy Ion Induced Effects in Nuclear Materials with Neutron and Synchrotron Radiation
Combined MeV/Nucleon Irradiation and High Energy Synchrotron X-ray Characterization of Nuclear Materials
Corrosion at the Surface of a Nuclear Fuel: In-Situ Radiolysis and X-ray Scattering from Thin Single-Crystal UO2 Films
In-Situ Studies of Dislocation Structure Evolution during Annealing of Neutron Irradiated Zr-2.5Nb Alloy
In Situ Carbothermic Reduction of Uranium Carbide and its High Temperature Cubic Phase
Isotope Specific Neutron Imaging of Nuclear Fuel Pellets
K1: Behavior of Deutride Particle in Zircaloy under Thermal Cycles and Stress Investigated by In-Situ Neutron Diffraction
K2: Characterization of Internal Strain During Incremental Loading of Zircaloy-2
K3: High Energy X-ray Diffraction Study of Deformation Behavior of Alloy HT-9
K4: In-Situ Synchrotron Investigations on the Deformation-induced Martensitic Transformation in Metastable Austenitic Steels with and without Oxygen-Enriched Nanoparticles
K5: Influence of Thermal Aging on the Tensile Properties of Alloy 617: An In-Situ Synchrotron X-ray Diffraction Investigation
K6: Investigation on Hydride Particle in Zircaloy-4 by Utilizing High Energy Synchrotron X-ray
K7: Microbeam X-ray Diffraction and TEM Characterization of Irradiation Effects by Fission Fragment Energy Xe Ion Beam
K8: Structural Investigation of UO2+x at Extreme Conditions by Synchrotron XRD Measurements
Measurements of H Solubility in Zirconium
Non-Destructive Grain Growth Study in Uranium dioxide Fuel Pellets Using Synchrotron Radiation
Strain Induced Phase Transformation in a Zirconium Alloy Investigated Using Synchrotron and Neutron Radiation
Synchrotron Radiation Study on 14YWT and MA957 ‪Nanostructured Ferritic Alloys‬‬
Temperature and Grain Size Dependent Deformation Mechanisms of Ultrafine Grained Austenitic Stainless Steel Studied by In Situ Neutron Diffraction
Utilization of Synchrotron X-ray Techniques for Microstructural Analyses in Irradiated Metallic Nuclear Fuels and Structural Materials


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