Abstract
A system was developed and tested to provide a deeper understanding of the fission gas release kinetics from nuclear fuel during thermal transients. Pressure, temperature, spectral data, and optical images were simultaneously collected during resistive sample heating, and all released gases were collected in liquid nitrogen-cooled charcoal traps. Standup testing was performed with a high-burnup nuclear fuel segment from rod section with an average local burnup of 77 GWd/tU. During heating, the segment released approximately 6 ± 2% of generated fission gas inventory after ramp heating to 460°C. Heating ceased when the sample ejected from the holder, as observed by constant imaging.
Original language | English |
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Article number | 154582 |
Journal | Journal of Nuclear Materials |
Volume | 584 |
DOIs | |
State | Published - Oct 2023 |
Funding
The authors gratefully acknowledge the work of Zachary Burns in initial fuel preparation, David Wilson for assistance with the electrical control box, the hot cell operations team for fuel transport and fueled test execution, and Dylan Richardson for fabrication of the SiC sample holder. This work was funded by the U.S. Department of Energy Office of Nuclear Energy Advanced Fuel Campaign . Notice: This manuscript has been authored by UT-Battelle LLC under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ).
Funders | Funder number |
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U.S. Department of Energy Office of Nuclear Energy Advanced Fuel Campaign | |
U.S. Department of Energy | |
UT-Battelle | DE-AC05-00OR22725 |
Keywords
- HBFF
- LOCA
- tFGR