ProgramMaster Logo
Conference Tools for Materials Science & Technology 2012
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Propose A Proceedings
Presenter/Author Tools
Organizer/Editor Tools
About this Symposium
Meeting Materials Science & Technology 2012
Symposium Materials Development for Nuclear Applications and Extreme Environments
Sponsorship
Organizer(s) Ram Devanathan, Pacific Northwest National Laboratory
Raul B. Rebak, GE Global Research
Kevin Fox, Savannah River National Laboratory
Ramprashad Prabhakaran, Idaho National Laboratory
Aladar A. Csontos, U. S. Nuclear Regulatory Commission
Kumar Sridharan, University of Wisconsin
Bill Lee, Imperial College London
Elizabeth Hoffman, Savannah River National Laboratory
Ramana G. Reddy, The University of Alabama
Scope Global expansion of nuclear power to meet the rising energy demand calls for the development of structural materials and fuels for advanced reactors. A related issue is the performance of materials under extreme conditions, such as elevated temperature, mechanical stress, high radiation dose, and corrosive environments.

This symposium will cover fundamental and applied science aspects of materials development for fission and fusion reactors, radiation detectors and extreme environments. In addition, the symposium will also focus on the lifetime extension of existing nuclear reactors. A key goal is to discuss the radiation response of all classes of materials—metals, ceramics, semiconductors, polymers and composite materials—to discover linkages and common threads. Presentations that combine experiment with theory, modeling and simulation to enhance our understanding of radiation effects in materials are especially encouraged. Abstracts are solicited in (but not limited to) the following topics:

• Fundamental science of radiation damage and defect processes
• Materials for extreme environments
• Advanced nuclear fuels
• Structural materials for fission and fusion reactors
• Ion irradiation effects in materials
• Radiation effects in nanomaterials
• Mechanical behavior of irradiated materials
• Lifetime extension of existing nuclear reactors
• Thermal conductivity degradation
• Materials for radiation detection
• Theory, modeling and simulation of radiation effects
• Education and public outreach
Abstracts Due 04/02/2012
Proceedings Plan Planned: Post-meeting proceedings
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

A Comparison of Structure and Properties of 9 and 18 Cr – Y2O3 Dispersion Strengthened Steels
Ageing and Toughness of a Mn-Ni-Mo PWR Steel
An Update on the Mechanical Properties of U-Mo Fuels
Application of a Hybrid Potts-Phase Field Model to Nuclear Materials
Atomistic Simulations of Ionic Conductivity and Radiation Tolerance of Ceramics
Characterization of U-Zr Alloys for Ultrahigh Burn-up Nuclear Fuels
Comparison of Stress Relaxation near a Notch in Unirradiated and Irradiated Zr-2.5Nb Pressure Tube Material
Computer Simulation of Displacement Cascades in Alpha Zirconium
Defect Morphology in Nanocrystalline Iron after Ion Irradiation
Effects of Pre-Injected Helium Interstitials on Heavy Ion Irradiated Inconel X-750
Effects of Proton Irradiation on Zirconium Carbide with Different Stoichiometry
Elaboration and Characterization of Titanium Carbide Monoliths Sintered through SPS, HIP and HP
Environmental Cracking of Chromium Containing Alloys in High Temperature Water
Interdiffusion between U-10wt.%Zr and Fe-15wt.%Cr–15wt.%Ni Diffusion Couples Annealed at 600, 650 and 700℃
Interface Affected Cascading In Nuclear Materials and Its Correlation with Bond Strength
Low Activation Materials for Nuclear-Grade Joining of SiC Components
Metallurgical Evolution during Hot Processing of a Ferritic ODS Stainless Steel Cladding Tubes
Microstructure Evolution during Cold Rolling and High Temperature Annealing of Alloy 617
Precursor Derived Nanostructured SiC for Next Generation Nuclear Applications
Radiation and Oxidation Stability of Thin Film Interfaces
Solute Diffusion To Dislocations under Irradiation: Si in Ni
TEM Analysis of Incoloy 800H Exposed to Molten LiF-NaF-KF
The Effect of Neutron Irradiation on Friction Stir Welded MA956 and MA754
The Investigation of the Electrochemical and Corrosion Behavior of AISI 304L Stainless Steel for Applications in Nuclear Waste Reprocessing Systems
Thermodynamics of Actinide Alloys: Application to RERTR Nuclear Fuels
Thermomechanical Damage and Microstructure Evolution during Creep in 9Cr Ferritic-Martensitic Steel
Thermophyical Properties of Thoria and ThO2-UO2 Mixed Oxide Fuels Using Atomic Level Simulations


Questions about ProgramMaster? Contact programming@programmaster.org