Andrew Nelson Section Head, Nuclear Fuel Development Contact NELSONAT@ORNL.GOV All Publications Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering Development of Standardized Property Requirements, Measurement Methods, and Reporting Guidance for Coatings Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory Fracture Strength Determination Methods for Ceramic Materials Applied to Uranium Dioxide Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing Performance of U3Si2 in an LWR following a cladding breach during normal operation Accident-Tolerant Fuel Development and Demonstration of a Methodology to Evaluate High Burnup Fuel Susceptibility to Pulverization under a Loss of Coolant Transient STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5% Initial development of an RIA envelope for dispersed nuclear fuel Other Power Reactor Fuels Fabrication and Characterization Methodology of Transformational Challenge Reactor Fuel Form Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels Fabrication of UN-Mo CERMET nuclear fuel using advanced manufacturing techniques Grain Boundary and Lattice Fracture Toughness of UO2 Measured Using Small-Scale Mechanics Production of 28 μm zirconium carbide kernels using the internal gelation process and microfluidics Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR... Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys Lithography-based Ceramics Manufacturing Technologies Progress on Synthesis of Low Content Inert Matrix Fuel Pellets... Separate effects irradiation testing of miniature fuel specimens... Oxidation of Spent Fuel During Fuel Handling Accidents Test Plan Pagination First page « First Previous page ‹â¶Ä¹ … Page 3 Current page 4 Page 5 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section
