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Linton, Kory D.
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (10/10 displayed)
- 2018In-cell Re-fabrication and Loss-of-coolant Accident (LOCA) Testing of High Burnup Commercial Spent Fuel
- 2018Assembly and Delivery of Rabbit Capsules for Irradiation of Reinforced Radiation Resistant SiC-SiC Composites in the High Flux Isotope Reactor
- 2018Design and Thermal Analysis for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
- 2018Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA
- 2018Completion of the Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor
- 2018Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
- 2017Transition Fracture Toughness Characterization of Eurofer 97 Steel using Pre-Cracked Miniature Multi-notch Bend Bar Specimens
- 2017Radiation Induced Segregation at Low Angle Grain Boundaries in Steels: NSUF 2017 Milestone Report
- 2017Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
- 2017In-pile Hydrothermal Corrosion Evaluation of Coated SiC Ceramics and Composites
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report
Completion of the Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor
Abstract
This document outlines the irradiation of silicon carbide cladding tube specimens in the High Flux Isotope Reactor at Oak Ridge National Laboratory. The cladding tube specimens consisted of monolithic, composite, and coated SiC specimens in order to test the effect of these various materials on the overall cladding performance during irradiation. A total of 18 specimens were irradiated for one cycle, with 9 specimens irradiated at low heat flux conditions and 9 specimens at high heat flux conditions. The specimens were inserted in cycle 475 in September 2017 and reached an average irradiation dose of approximately 2.6 dpa.