Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient

Doyle, Peter; Harp, Jason

doi:10.1016/j.jnucmat.2023.154582

Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO₂ Nuclear Fuel During Thermal Transient

Journal Article · Thu Jun 15 00:00:00 EDT 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154582· OSTI ID:1986224

Doyle, Peter ^[1]; ^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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. Here, heating ceased when the sample ejected from the holder, as observed by constant imaging.

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1986224

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 584; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (8)

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Fission gas release behaviour of a 103GWd/tHM fuel disc during a 1200°C annealing test Noirot, J.; Pontillon, Y.; Yagnik, S. Journal of Nuclear Materials, Vol. 446, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.002	journal	March 2014
On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM Restani, R.; Horvath, M.; Goll, W. Journal of Nuclear Materials, Vol. 481 https://doi.org/10.1016/j.jnucmat.2016.08.023	journal	December 2016
Fission gas release from UO2 nuclear fuel: A review Rest, J.; Cooper, M. W. D.; Spino, J. Journal of Nuclear Materials, Vol. 513 https://doi.org/10.1016/j.jnucmat.2018.08.019	journal	January 2019
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data Chadwick, M. B.; Herman, M.; Obložinský, P. Nuclear Data Sheets, Vol. 112, Issue 12 https://doi.org/10.1016/j.nds.2011.11.002	journal	December 2011
Integral LOCA fragmentation test on high-burnup fuel Capps, Nathan; Yan, Yong; Raftery, Alicia Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110811	journal	October 2020
Corrigendum to “Integral LOCA fragmentation test on high-burnup fuel” [Nucl. Eng. Design (2020) 367 110811, ISN 0029-5493] Capps, Nathan; Yan, Yong; Raftery, Alicia Nuclear Engineering and Design, Vol. 377 https://doi.org/10.1016/j.nucengdes.2021.111197	journal	June 2021
An Assessment of the Fuel Pulverization Threshold During LOCA-Type Temperature Transients Turnbull, J. A.; Yagnik, S. K.; Hirai, M. Nuclear Science and Engineering, Vol. 179, Issue 4 https://doi.org/10.13182/NSE14-20	journal	April 2015

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Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient

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References (8)

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Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO₂ Nuclear Fuel During Thermal Transient