NSUF 25-5295: High-Temperature In-Situ Micro-Tensile Testing of FFTF-Irradiated HT9 Cladding from U-10Zr Fuel Pins

Current HT-9 creep and deformation models within the BISON framework consistently exhibit significant discrepancies between simulated and experimentally observed HT-9 cladding behavior, primarily due to a lack of experimental data under prototypical reactor conditions. Critical factors that need to be considered for more accurate cladding predictions include fuel-cladding chemical interaction (FCCI), precipitate evolution, intermetallic phase formation, and radiation damage. To gather mechanical property data that is more relevant for simulations predicting in-pile fuel-cladding behavior, this work involves performing micro-tensile tests on HT-9 cladding from a U-10Zr fuel irradiated in the Fast Flux Test Facility (FFTF). This experiment aims to define the prototypical mechanical properties of HT-9 cladding, elucidate the effects of temperature and radiation on these properties, and highlight the structure-property relationships in HT-9. Ultimately, this will aid in the development of more robust fuel performance models needed for qualifying HT-9 clad U-Zr-based fuels.

Anformazio gehigarria

Eremua	Balorea
Award Announced Date	2025-08-06T10:10:01.907
Awarded Institution	Idaho National Laboratory
Facility Tech Lead	Alina Montrose
Irradiation Facility
PI	Guang Yang
PI Email	[email protected]
Project Type	RTE
RTE Number	None