Christian M Petrie Group Leader, Senior R&D Staff Contact petriecm@ornl.gov | 865.576.0827 All Publications Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux... Oak Ridge National Laboratory Compilation of AMMT Quality Assurance Procedures Enhanced backscatter and unsaturated blue wavelength shifts in F-doped fused silica optical fibers exposed to extreme neutron radiation damage Development of Optical Fiber-Based Sensors for Nuclear Microreactor Structural Health Monitoring Radiation-induced negative optical nonlinearities in fused silica, sapphire, and borosilicate glass High Flux Isotope Reactor Irradiation of Self-Powered Neutron Detectors A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification... Analysis of WIRE-21 SPND and Optical Fiber Sensor Measurements UCO TRISO Minifuel FY23 NSUF-Kairos Power Post-Irradiation Examination Status Report Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix Testing of an Optical Fiber--Based Gamma Thermometer in the High Flux Isotope Reactor Gamma Irradiation Facility Air Ingress and DLOFC Studies in Scaled HTGR Geometry Using Additively Manufactured TCR Fuel Elements Toward Local Core Outlet Temperature Monitoring in Gas-Cooled Nuclear Reactors Using Distributed Fiber-Optic Temperature Sensors Development, Testing, and Validation of Fabry-Pérot Cavity Acoustic Sensors for Microreactor Applications Multiscale Modeling of Radiation Damage in UO2 under Accelerated Burnup Conditions Non-Nuclear Advanced Controls Testbed Methods for Continuously Resolving Spectral Shifts in Distributed Optical Fiber Sensors Irradiated to Extreme Neutron Fluence In-Rod Sensor System Overview, Benefits and Recent Irradiation Test Results... Irradiation Testing of Fully Ceramic Microencapsulated (FCM) Fuel Compacts in the High Flux Isotope Reactor... Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification WIRE-21 Experiment Irradiation Conditions and In-Situ Data Collection Summary of Methodology for Mitigating Risks Associated with Licensing and Qualifying AM Nuclear Materials Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matri... Nuclear fuel irradiation testbed for nuclear security applications Embedding thermocouples in SS316 with laser powder bed fusion*... Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Advanced Fuel Fabrication and Instrumentation Group User Facilities High Flux Isotope Reactor Manufacturing Demonstration Facility
