Silcon Carbide Cladding Lead Test Rod Development-Phase 1 Research, development, and fabrication of Silicon Carbide cladding specimens for research reactor insertion, irradiation, and post-irradiation examinations by 2030. The objective of this program is to advance the scientific and technological maturity of silicon carbide cladding for nuclear fuel rods for future use in commercial light water reactors.
Funding Opportunity — DOE - DOE / U.S. Department of Energy
PSC N/A · NAICS N/A · Ref DE-FOA-0003577
The program seeks to support research and development of SiC cladding technology, including mechanical, thermal-hydraulic, high temperature, and corrosion testing for both unirradiated and irradiated SiC cladding samples. Irradiation campaigns in research reactors (e.g., INL ATR, ORNL HFIR, MITR) and Post Irradiation Evaluations (PIEs) are expected to provide irradiation performance data for fuel vendor licensing and accident analyses methods needed for NRC licensing review. Improvements in SiC/SiC composite cladding fabrication methods are expected to be made.
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Source: DOE - DOE (solicitation DE-FOA-0003577), retrieved via a public procurement portal. View the official posting, and always confirm requirements and deadlines with the issuing agency.