Peter Doyle Postdoctoral Research Associate Contact DOYLEPJ@ORNL.GOV All Publications Status of the Fuel Fragment Dispersal Studies at 91°µÍø Final CRADA Report – NFE-23-09937: Post-Irradiation Examination to Quantify Irradiation-Induced Bowing of SiGA® Silicon Carbide Composite Structures FUEL FRAGMENT DISPERSAL DURING A POSTBURST VIBRATION EVENT... Dispersal of high-burnup fuel fragment surrogate particles during and after loss-of-coolant accident tests Low-Pressure and Fluidized-Bed Chemical Vapor Deposition of PyC and ZrC for Space Nuclear Propulsion Characterization of fluidized bed chemical vapor deposition ZrC coatings on PyC/YSZ kernels deposited under differing conditions Parallel Irradiation Testing to Support Accelerated Down-Selection of Advanced Fuels The effect of powder feedstock and heat treatment on the thermal and mechanical properties of binder jet printed ZrC Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment Exploration of LIBS as a novel and rapid elemental mapping technique of nuclear fuels in the form of surrogate TRISO particle... Chemical vapor deposition of ZrC coatings for Space Nuclear Propulsion High-temperature oxidation behavior of the SiC layer of TRISO particles in low-pressure oxygen Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Specimen Size Artifacts Associated with a Glovebox Deployable Laser Flash Diffusivity Measurement System Development and Standup Testing of a System to Observe Fission Gas Release During Transient Heating of Nuclear Fuel Element S... MICROSTRUCTURAL ANALYSIS OF IRON-CHROMIUM-ALUMINUM SAMPLES EXPOSED TO LOCA-TYPE CONDITIONS FOLLOWED BY QUENCH Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding Hydrothermal corrosion behavior of CVD SiC in high temperature water The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC Evaluation of the Effects of Neutron Irradiation on First-Generation Corrosion Mitigation Coatings on SiC for Accident-Tolerant Fuel Cladding Extracting meaningful standard enthalpies and entropies of activation for surface reactions from kinetic rates Characterization of PVD Cr, CrN, and TiN coatings on SiC Evaluation of the Corrosion Kinetics of SiC with and without Mitigation Coatings in LWR Chemistries... Hydrothermal Corrosion of Coatings on Silicon Carbide in Boiling Water Reactor Conditions Pagination Current page 1 Page 2 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 Nuclear Fuel Element Performance Group
