ProgramMaster Logo
Conference Tools for 2017 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Symposium
Meeting 2017 TMS Annual Meeting & Exhibition
Symposium Nanostructured Materials for Nuclear Applications II
Sponsorship TMS Materials Processing and Manufacturing Division
TMS Structural Materials Division
TMS: Nanomechanical Materials Behavior Committee
TMS: Nuclear Materials Committee
Organizer(s) Cheng Sun, Idaho National Laboratory
Khalid Hattar, Sandia National Laboratories
Celine Hin , Virginia Tech
Fei Gao , University of Michigan
Osman Anderoglu , Los Alamos National Laboratory
Mitra Taheri , Drexel University
Haiming Wen , Idaho State University
Scope A paramount challenge in the development of advanced nuclear reactors is to discover advanced materials that can operate reliably in extreme service conditions, i.e. neutron, high temperatures, corrosive environments, etc. nanostructured materials with a high volume fraction of buried interfaces are theorized to have improved resistance to irradiation. Thus, there is an increasing need to understand how interfacial structures mitigate radiation-induced damage and to design stable nanostructured materials that can survive in these severe irradiation conditions.

The aim of this symposium is to provide a forum for the discussion on nanostructured materials stability under extreme conditions. This includes understanding the role of grain boundary and interfacial structures and chemistry on the radiation tolerance and microstructural stability. Presentations on experimental, theoretical, and modeling research are solicited. Topic areas for this symposium include, but are not limited to:

1. Manufacturing, characterization, and mechanical testing of nano-engineered materials.
2. Radiation damage of nano-featured materials, including nanoparticle-dispersion-strengthened composites, nanocrystalline materials, multilayer structured materials etc.
3. The effects of interfaces (free surfaces, grain boundaries, phase boundaries, etc) on the radiation tolerance of materials
4. Nano-mechanical testing of irradiated materials.
5. Nanostructured waste form materials and fuels. (Joint session with symposium: “Ceramic Materials for Nuclear Energy Research and Applications”)
6. Atom probe tomography characterization of irradiated materials. (Joint session with symposium: “Alloy Phase Chemistry at the Atomic Level: Opportunities and Challenges”)
Abstracts Due 07/17/2016
Proceedings Plan Planned: Supplemental Proceedings volume
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

Advanced Manufacturing of Nanostructured Ferritic Steels with Enhanced Irradiation Performance for Nuclear Applications
Atom Probe Tomography Study of Neutron Irradiated U-Mo Fuel
Computational Simulation of Threshold Displacement Energy of GaAs
Defect Evolution in Stannate Pyrochlores under Swift Heavy Ion Irradiation
Design of Radiation-resistant Alloys
Evolution of Microstructures and Mechanical Properties of Zr-containing Ferritic Alloys under Self-ion Irradiation
Exploring the In-plane Distribution of Helium Bubbles at Cu/V Interfaces
First-principles Study of Nano-layered Ceramic Coatings for U-Mo/Al Dispersion Fuel
In-situ TEM Study of Defect-grain Interactions under Irradiation in Bulk Severe Plastically Deformed Model Ni Alloys
Irradiation Response of Nanostructured Oxides to Ionization and Displacement Damage
J-38: Grain Boundary Density Dependence of Radiation Induced He Bubble Formation in Nanocrystalline Fe and Ni Thin Films
Kinetic Mote Carlo Simulation of Radiation-induced Segregation in Quaternary Fe-Ti- Y-O
Kinetics of Initial Phase Separation and Coarsening of Nanoscale Phase in Fe–Cr Alloys
Magnetic and Electrical Responses of Nanomaterials under Irradiation - New Type of Radiation Detection
Microstructural Characterization of ATR Irradiated Cu/Nb Nanolayered Composites
Molecular Dynamic Cascade Simulations of Yttria Nanoclusters in an Alpha Fe Matrix
Nano-particles Control for High Performance ODS Steels
Period-thickness Dependent Responses of Cu/W Multilayered Nanofilms to Ions Irradiation under Different Ion Energy
Point Defect Diffusion in Oxide Dispersion Strengthened Steels
Probing Nanoscale Damage Gradients in Irradiated Materials with Spherical Nanoindentation
Radiation Effects on the Mechanical Properties of Nanoporous Gold
Radiation Interaction of Nanostructured Ceramics
Radiation Resistance of a FeCr Model Alloy Nanostructured by Severe Plastic Deformation
Search for Radiation Resistance Materials: As Revealed by Computer Simulations
Stability and Self-ion Irradiation Damage in Nanocrystalline Tungsten and Solute-stabilized Tungsten Alloys
Stability of 14YWT Nanostructured Ferritic Alloys under Irradiation and Thermal Aging
Synthesis and Microstructural Characterization of Zirconium Oxide Dispersion Strengthened Model Alloy and 9 Cr Ferritic Steel
The Two-step Nucleation of G-phase in Ferrite: The Critical Size and Composition for the Structural Change of Solute Clusters
Thermal Conductivity of Uranium
Understanding and Predicting Nanoscale Precipitate Formation and Associated Reactor Pressure Vessel Embrittlement
Using Atom Probe Tomography and Neutron Inventory Simulation to Investigate Neutron-Irradiation-Induced Nano-Scale Second Phase Precipitation Chemistry in Pure Tungsten Irradiated at HFIR
Varying Responses of Nanocrystalline Structures to Assorted Irradiation Conditions


Questions about ProgramMaster? Contact programming@programmaster.org