Abstract
In this work, we present post-irradiation examination (PIE) results on annular MOX with HT-9 cladding pins irradiated in the Fast Flux Test Facility (FFTF) at medium burnup. PIE results highlight different irradiation behavior (e.g., Cs migration behavior) between pins with different initial plutonium content. No fuel performance simulation results are available at this time to evaluate the irradiation temperatures of the pins, but it is likely that the higher Pu content of the L-type pins resulted in higher temperatures due to the larger thermal conductivity decrease with higher Pu content. The higher temperature is likely to be the major factor causing Cs axial migration. Measurements of microstructural features such as central hole size have been collected to be used for future comparison with model predictions.
Original language | English |
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Pages | 735-737 |
Number of pages | 3 |
State | Published - 2020 |
Externally published | Yes |
Event | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019 |
Conference
Conference | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 |
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Country/Territory | United States |
City | Seattle |
Period | 09/22/19 → 09/27/19 |
Funding
The work presented in this paper was supported by the U.S. Department of Energy, Nuclear Science User Facility (NSUF) CINR Project 17-12976.