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Gallagher, Ryan C.
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report
Design and Thermal Analysis for Irradiation of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor
Abstract
This report provides a summary of the irradiation vehicle design and thermal analysis of SiC joint specimens planned for irradiation in the flux trap of the High Flux Isotope Reactor (HFIR). Two different capsule designs will be used to accommodate the two different specimen geometries: a small torsion joint specimen geometry to measure mechanical and thermal properties, and a tube and end plug joint representative cladding geometry to demonstrate strength and hermeticity retention. The capsule designs, with target temperatures of 350° and 750°C, will accommodate either sixteen torsion joint specimens or one tube end plug joint specimen. Three joint variations will be studied in each capsule design: a hybrid SiC (preceramic polymer with chemical vapor deposition (CVD) SiC), a transient eutectic phase (TEP) process, and an oxide process.