Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale

© 2020 The anticipated benefits of large grains in Cr2O3-doped UO2 pellets include improved mechanical and fission gas retention properties. To support the assessment of fission gas release (FGR) from doped pellets, the impact of doping on fission gas diffusivity for in-reactor conditions must be un...

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Main Authors: Cooper, Michael WD, Pastore, Giovanni, Che, Yifeng, Matthews, Christopher, Forslund, Axel, Stanek, Christopher R, Shirvan, Koroush, Tverberg, Terje, Gamble, Kyle A, Mays, Brian, Andersson, David A
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Language:English
Published: Elsevier BV 2023
Online Access:https://hdl.handle.net/1721.1/147649
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author Cooper, Michael WD
Pastore, Giovanni
Che, Yifeng
Matthews, Christopher
Forslund, Axel
Stanek, Christopher R
Shirvan, Koroush
Tverberg, Terje
Gamble, Kyle A
Mays, Brian
Andersson, David A
author2 Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
author_facet Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Cooper, Michael WD
Pastore, Giovanni
Che, Yifeng
Matthews, Christopher
Forslund, Axel
Stanek, Christopher R
Shirvan, Koroush
Tverberg, Terje
Gamble, Kyle A
Mays, Brian
Andersson, David A
author_sort Cooper, Michael WD
collection MIT
description © 2020 The anticipated benefits of large grains in Cr2O3-doped UO2 pellets include improved mechanical and fission gas retention properties. To support the assessment of fission gas release (FGR) from doped pellets, the impact of doping on fission gas diffusivity for in-reactor conditions must be understood. In this work, we tackle this issue by informing the fission gas model within the BISON fuel performance code using material models developed at the atomic scale. The investigation of intra-granular fission gas diffusivity in Cr2O3-doped UO2 is carried out by adapting a cluster dynamics model that, accounting for UO2 thermochemistry, is capable of describing Xe diffusion under irradiation in undoped UO2 as the starting point. Using a thermodynamic analysis, it is shown that in stoichiometric UO2 with additions of Cr2O3, the oxygen potential is defined by the Cr-Cr2O3 two-phase equilibrium. Using the cluster dynamics model, the predicted Xe diffusivity in doped UO2 was significantly increased in both the intrinsic and irradiation-enhanced regimes compared to undoped UO2, as a result of higher concentrations of uranium and oxygen vacancies, respectively. This is a consequence of the more oxidizing conditions at high temperature, and more reducing conditions at low temperature, as a result of doping. Arrhenius functions have been fitted to the cluster dynamics results to enable implementation of the new diffusivities in the BISON fission gas behavior model. BISON simulations were carried out, showing the competing effects of the enlarged grains and the new fission gas diffusivity model, which act to suppress and enhance fission gas release, respectively. The new physics-informed model was validated against in-reactor experimental measurements under normal operation. Additionally, benchmarking was carried out for power ramp conditions. The predicted fission gas release agreed well with the experimental data, showing noticeable improvements over the standard UO2 model.
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spelling mit-1721.1/1476492023-01-25T03:39:39Z Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale Cooper, Michael WD Pastore, Giovanni Che, Yifeng Matthews, Christopher Forslund, Axel Stanek, Christopher R Shirvan, Koroush Tverberg, Terje Gamble, Kyle A Mays, Brian Andersson, David A Massachusetts Institute of Technology. Department of Nuclear Science and Engineering © 2020 The anticipated benefits of large grains in Cr2O3-doped UO2 pellets include improved mechanical and fission gas retention properties. To support the assessment of fission gas release (FGR) from doped pellets, the impact of doping on fission gas diffusivity for in-reactor conditions must be understood. In this work, we tackle this issue by informing the fission gas model within the BISON fuel performance code using material models developed at the atomic scale. The investigation of intra-granular fission gas diffusivity in Cr2O3-doped UO2 is carried out by adapting a cluster dynamics model that, accounting for UO2 thermochemistry, is capable of describing Xe diffusion under irradiation in undoped UO2 as the starting point. Using a thermodynamic analysis, it is shown that in stoichiometric UO2 with additions of Cr2O3, the oxygen potential is defined by the Cr-Cr2O3 two-phase equilibrium. Using the cluster dynamics model, the predicted Xe diffusivity in doped UO2 was significantly increased in both the intrinsic and irradiation-enhanced regimes compared to undoped UO2, as a result of higher concentrations of uranium and oxygen vacancies, respectively. This is a consequence of the more oxidizing conditions at high temperature, and more reducing conditions at low temperature, as a result of doping. Arrhenius functions have been fitted to the cluster dynamics results to enable implementation of the new diffusivities in the BISON fission gas behavior model. BISON simulations were carried out, showing the competing effects of the enlarged grains and the new fission gas diffusivity model, which act to suppress and enhance fission gas release, respectively. The new physics-informed model was validated against in-reactor experimental measurements under normal operation. Additionally, benchmarking was carried out for power ramp conditions. The predicted fission gas release agreed well with the experimental data, showing noticeable improvements over the standard UO2 model. 2023-01-24T14:54:47Z 2023-01-24T14:54:47Z 2021 2023-01-24T14:29:47Z Article http://purl.org/eprint/type/JournalArticle https://hdl.handle.net/1721.1/147649 Cooper, Michael WD, Pastore, Giovanni, Che, Yifeng, Matthews, Christopher, Forslund, Axel et al. 2021. "Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale." Journal of Nuclear Materials, 545. en 10.1016/J.JNUCMAT.2020.152590 Journal of Nuclear Materials Creative Commons Attribution-NonCommercial-NoDerivs License http://creativecommons.org/licenses/by-nc-nd/4.0/ application/pdf Elsevier BV DOE repository
spellingShingle Cooper, Michael WD
Pastore, Giovanni
Che, Yifeng
Matthews, Christopher
Forslund, Axel
Stanek, Christopher R
Shirvan, Koroush
Tverberg, Terje
Gamble, Kyle A
Mays, Brian
Andersson, David A
Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title_full Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title_fullStr Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title_full_unstemmed Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title_short Fission Gas Diffusion and Release for Cr 2 O 3 -Doped UO 2: From the Atomic to the Engineering Scale
title_sort fission gas diffusion and release for cr 2 o 3 doped uo 2 from the atomic to the engineering scale
url https://hdl.handle.net/1721.1/147649
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