Peter J Doyle Postdoctoral Research Associate Contact doylepj@ornl.gov | 865.241.4237 All Publications 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 particles 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-Tolera... 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... Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding... Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings... Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings... Key Links Curriculum Vitae ORCID ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group