Christian Petrie Group Leader, Senior R&D Staff Contact PETRIECM@ORNL.GOV All Publications In-Pile OFDR Sensing with Fiber Bragg Gratings in Sapphire Optical Fiber High-dose temperature-dependent neutron irradiation effects on the optical transmission and dimensional stability of amorphous fused silica Assessment of Pre-Irradiation SiC CMC Joint Performance in Representative Cladding Geometries Assembly and Delivery of Capsules for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor Embedment of sensors in ceramic structures Thermal and Neutronic Analysis for Irradiation of Advanced Neutron Absorbing Material in the High Flux Isotope Reactor Separate effects irradiation testing of miniature fuel specimens... Length Dependence of Severe Accident Test Station Integral Testing High-temperature strain monitoring of stainless steel using fiber optics embedded in ultrasonically consolidated nickel layer... Embedding Fiber Optic Strain Sensors Using Ultrasonic Additive Manufacturing Embedded Fiber-Optic Sensors for In-Pile Applications X-Ray Computed Tomography Analysis of Neutron-Irradiated SiC Composite Tube Suitability of Type-II Fiber Bragg Gratings in Silica Optical Fiber for Temperature Sensing in TREAT Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopy Overview of General Atomics SiGAâ„¢ SiC-SiC Composite Development for Accident Tolerant Fuel Compressible Metal Foils for Temperature Control During Irradiation... Capacitance-Based Dimensional Change Sensors for In-Pile Materials Measurements Separate Effects Miniature Fuel Irradiation Testing to Support Fuel Safety Irradiation Creep Testing of SiC Rabbit Specimens in the High Flux Isotope Reactor Embedded metallized optical fibers for high temperature applications Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determinat... Irradiation Test Plan for Fully Ceramic Microencapsulated Fuels Nano-scale microstructure damage by neutron irradiations in a novel Boron-11 enriched TiB2 ultra-high temperature ceramic Ceramic Fuel for Advanced High Temperature Gas Reactors Accelerated Irradiation Testing of Miniature Nuclear Fuel and Cladding Specimens Pagination First page « First Previous page ‹â¶Ä¹ … Page 5 Current page 6 Page 7 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 Fuel Cladding and Core Internals Group User Facilities Manufacturing Demonstration Facility
