Session:?Advances in Materials Testing and Analysis
Time:?Wednesday afternoon
Chair:?John Lambert
Alternate Chair:?Carl Beyer
Room:?Council
Tracking ID | Title |
125726 | Uranium-Based Catalysts |
116030 | Demonstration of Millimeter-Wave Waste Glass Melter Monitoring Technology for Viscosity and Salt-Layer Formation |
125502 | Development of Non-destructive Post-irradiation Examination Technique Using High-energy X-ray Computer Tomography |
125779 | Polonium Contamination Removal from Stainless Steel by Baking Method |
123181* | Estimating Source Terms for Diverse Spent Nuclear Fuel Forms |
125983 | Radiation Effects in ZrC |
125811 | Effects of Light and Heavy Element Irradiation in Zirconium Nitride |
From session 2
Session:?Development & Testing of Fuels for Advanced Reactors
Time:?Thursday morning
Chair:?Rob Hanrahan
Alternate:?Todd Allen
Room:?Council
Tracking ID | Title |
125687 | Thermochemistry of Defects and Oxygen Diffusion in PuO2-x |
125978 | Depleted Uranium Oxide Modification and Fabrication for Mixed Oxide Fuel Development at the Los Alamos National Laboratory |
125805 | Removal of Iron and Aluminum Impurities from Uranyl Nitrate Solutions for AGR Feedstock |
125796 | Measurements of Gap Conductance in Nuclear Fuels |
125700 | Radionuclide Release from Mixed-Oxide Fuel under Severe Accident Conditions |
126237 | Development of Mixed Carbide Fuels in Support of the AFCI Program |