The Nuclear Technology R&D program has significant experience at qualifying metallic fuels for fast reactor applications. In this process, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. Analysis of a duct made of HT-9 after irradiation to a total dose of 155 dpa at temperatures ranging from 370 to 510°C was completed including results from tensile, charpy impact and fracture toughness testing. Detailed microstructural analysis has also been performed with transmission electron microscopy. This has created a baseline for which new ferritic/martensitic produced through wrought and additive manufacturing processs have been developed with improved radiation tolerant properties. A summary of previous research will be presented along with recent progress in developing and testing improved radiation tolerant materials.
2022-04-06 08:00:00
