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.

Thông tin khác

Miền	Giá trị
Awarded Institution	Idaho National Laboratory
DOI	10.46936/NSUF/60013888
Embargo End Date	2027-03-26
Facility Tech Lead	Alina Montrose
NSUF Call	FY 2025 RTE 1st Call
PI	Guang Yang
PIE Facilities	Irradiated Materials Characterization Laboratory
Prep Facilities	Irradiated Materials Characterization Laboratory
Project Member	Dr. Yachun Wang, Postdoc Research Associate - Idaho National Laboratory (https://orcid.org/0000-0002-4952-3633)
Project Member	Mr. Bao-Phong Nguyen, Graduate Student - University of Florida (https://orcid.org/0000-0003-3928-6256)
Project Member	Dr. Guang Yang, Research Associate - Idaho National Laboratory (https://orcid.org/0000-0001-7570-7463)
Project Type	RTE