Microstructure-Level Modeling of Stage 3 Fission Gas Release in UO&lt;sub&gt;2&lt;/sub&gt; Fuel

Aagesen, Larry K.; Schwen, Daniel; Zhang, Yongfeng

doi:10.2172/1472129

“…In FY17, the effort has been focused on the development of a phase field recrystallization model for high-burnup structure formation in oxide fuels, a phase field model for studying stage-3 fission gas release, a phase-field model for irradiation-enhanced densification in UO 2 , a quantitative model for hydride morphology in Zirconium based claddings, and the calculation of hydrogen diffusivity under stress in various Zirconium based alloys as cladding candidates. Separated reports have been generated to describe the progress with appropriate amount of details [12][13][14][15][16]. Here, a brief summary is provided to guide interested readers for the overall accomplishments to guide interested readers.…”

Section: Introductionmentioning

confidence: 99%

FY17 end of year MARMOT materials model development update

Zhang

¹

,

Schwen

²

,

Aagesen

³

et al. 2017

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This document summarizes the lower length scale progress made in FY17 in developing materials models for fuel performance modeling of oxide fuels and their implementation in the MARMOT code. The progress covers the development of a phase field recrystallization model for high-burnup structure formation in oxide fuels, a phase field model for studying stage-3 fission gas release in UO 2 , a phase-field model for irradiation-enhanced densification in UO 2 , a quantitative model for hydride morphology in Zirconium based cladding, and the calculation of hydrogen diffusivity under stress in various Zirconium based alloys as cladding candidates. Further development in the MARMOT code has been carried out as well to improve the multiphase, multi-component phase field model, the representation of interfacial energy in the Kim-Kim-Suzuki model, and the description of interfacial stress. For most of the above, separated reports have been generated with detailed description. Here a brief summary is provided, with references pointing to the detailed reports or publications to guide interested readers.

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Multiphysics Modeling of Nuclear Materials

Spencer¹,

Schwen²,

Hales³

2020

Handbook of Materials Modeling

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The operating environment of nuclear reactors presents many unique challenges both for the materials comprising fuel elements (Olander 1976) and other structural components within and surrounding the reactor (Zinkle and Was 2013). These environmental challenges are due to the simultaneous exposure to conditions from multiple physical systems, including high temperatures, high radiation fluxes, aggressive chemical environments, and mechanical loading. Numerical simulation has been used for multiple decades as a tool for understanding the behavior of various components in this environment. As these tools have been developed to increasing levels of sophistication, they have been used increasingly both for engineering analysis of components, as well as for simulating the processes of microstructure evolution, which lead to changes in the engineering properties of interest in the materials used in these components. In some cases, the behavior of a single physics can be considered independently, simply because the response of one system does not change the conditions a component or material is subject to in other physical systems. For example, a component may be subjected to mechanical loading and thermal expansion due to elevated temperatures, but often, the mechanical response has a negligible effect on the thermal environment, so the temperature field can simply be imposed as a boundary condition to the mechanical model. However, there are also many scenarios in which the response to one physics has a strong effect on other physics. In the thermal/mechanical example, if the mechanical response of that component significantly changes its configuration, that could alter paths for heat transfer, and have a dramatic effect on the thermal field. In such a case, the simulation should account for two-way feedback between the models of these physical systems to accurately represent its response.

show abstract

Multiphysics Modeling of Nuclear Materials

Spencer¹,

Schwen²,

Hales³

2018

Handbook of Materials Modeling

Self Cite

View full text Add to dashboard Cite

The operating environment of nuclear reactors presents many unique challenges both for the materials comprising fuel elements (Olander 1976) and other structural components within and surrounding the reactor (Zinkle and Was 2013). These environmental challenges are due to the simultaneous exposure to conditions from multiple physical systems, including high temperatures, high radiation fluxes, aggressive chemical environments, and mechanical loading. Numerical simulation has been used for multiple decades as a tool for understanding the behavior of various components in this environment. As these tools have been developed to increasing levels of sophistication, they have been used increasingly both for engineering analysis of components, as well as for simulating the processes of microstructure evolution, which lead to changes in the engineering properties of interest in the materials used in these components. In some cases, the behavior of a single physics can be considered independently, simply because the response of one system does not change the conditions a component or material is subject to in other physical systems. For example, a component may be subjected to mechanical loading and thermal expansion due to elevated temperatures, but often, the mechanical response has a negligible effect on the thermal environment, so the temperature field can simply be imposed as a boundary condition to the mechanical model. However, there are also many scenarios in which the response to one physics has a strong effect on other physics. In the thermal/mechanical example, if the mechanical response of that component significantly changes its configuration, that could alter paths for heat transfer, and have a dramatic effect on the thermal field. In such a case, the simulation should account for two-way feedback between the models of these physical systems to accurately represent its response.

show abstract

Microstructure-Level Modeling of Stage 3 Fission Gas Release in UO<sub>2</sub> Fuel

Cited by 3 publications

References 29 publications

FY17 end of year MARMOT materials model development update

FY17 end of year MARMOT materials model development update

Multiphysics Modeling of Nuclear Materials

Multiphysics Modeling of Nuclear Materials

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