Search Results - "Gamble, Kyle A."
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Modeling fission product diffusion in TRISO fuel particles with BISON
Published in Journal of nuclear materials (01-05-2021)“…•BISON is now capable of computing diffusion of silver, cesium, and strontium.•BISON converges to the exact solution at the expect rate for test…”
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TRISO particle fuel performance and failure analysis with BISON
Published in Journal of nuclear materials (01-05-2021)“…Because of its widespread use in multiple advanced reactor concepts, the ability to accurately simulate tri-structural isotropic (TRISO) fuel performance is…”
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Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale
Published in Journal of nuclear materials (01-03-2021)“…The anticipated benefits of large grains in Cr2O3-doped UO2 pellets include improved mechanical and fission gas retention properties. To support the assessment…”
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A phase-field model of quasi-brittle fracture for pressurized cracks: Application to UO2 high-burnup microstructure fragmentation
Published in Theoretical and applied fracture mechanics (01-06-2022)“…In this paper, we present a phase-field model of quasi-brittle fracture with pressurized cracks, with dedicated applications for polycrystalline materials. The…”
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Phase-field simulations of intergranular fission gas bubble behavior in U3Si2 nuclear fuel
Published in Journal of nuclear materials (01-12-2020)“…U3Si2 is a potential accident-tolerant fuel that shows promise due to its high thermal conductivity and higher uranium density relative to UO2. However, its…”
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Rate theory scenarios study on fission gas behavior of U3Si2 under LOCA conditions in LWRs
Published in Nuclear engineering and design (01-01-2018)“…•Rate theory fission gas model for U3Si2 was developed for power transients in LWRs.•Model parametrization was conducted based on experimental and…”
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Fission gas diffusion and release for Cr 2 O 3 -doped UO 2 : From the atomic to the engineering scale
Published in Journal of nuclear materials (01-03-2021)Get full text
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Comparing the impact of thermal stresses and bubble pressure on intergranular fracture in UO2 using 2D phase field fracture simulations
Published in Journal of nuclear materials (01-02-2023)“…UO2 fuel fragmentation and pulverization during loss-of-coolant accidents (LOCAs) is an ongoing safety concern that has gained importance due to recent…”
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Modeling fission product diffusion in TRISO fuel particles with BISON
Published in Journal of nuclear materials (11-02-2021)“…Diffusion of fission products in intact TRISO particles depends on particle geometry, fission product source rates, time, temperature, and…”
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Gaseous swelling of U3Si2 during steady-state LWR operation: A rate theory investigation
Published in Nuclear engineering and design (01-10-2017)“…•Rate theory model for U3Si2’s fission gas behavior in LWRs was developed.•Sensitivity of the key parameters was analyzed to examine the model…”
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Mechanistic verification of empirical UO2 fuel fracture models
Published in Journal of nuclear materials (02-07-2021)“…Standard UO2 fuel pellets used in light-water reactors fracture during irradiation due to the large thermal gradient in the radial direction. Over the decades,…”
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An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
Published in Journal of nuclear materials (01-08-2017)“…Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel cladding for increased accident tolerance. An analysis of the response of…”
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Multidimensional modeling of fuel-cladding friction in an LWR fuel rod
Published in Nuclear engineering and design (01-08-2024)“…Solving finite element problems with friction often increases the level of difficulty to obtain properly converged solutions. This type of challenge becomes…”
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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions
Published in Journal of nuclear materials (15-08-2019)“…In this work, we present a model of fission gas behavior in U3Si2 under light water reactor (LWR) conditions for application in engineering fuel performance…”
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Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2
Published in Journal of nuclear materials (01-11-2021)“…U3Si2 is an advanced fuel candidate due to its relatively high fissile density and attractive thermal properties. Compared to standard UO2 fuel, there are…”
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Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale
Published in Journal of nuclear materials (20-10-2020)“…Here, the anticipated benefits of large grains in Cr2O3-doped UO2 pellets include improved mechanical and fission gas retention properties. To support the…”
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Rate theory scenarios study on fission gas behavior of U 3 Si 2 under LOCA conditions in LWRs
Published in Nuclear engineering and design (01-01-2018)“…Fission gas behavior of U3Si2 under various loss-of-coolant accident (LOCA) conditions in light water reactors (LWRs) was simulated using rate theory. A rate…”
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A layered 2D computational framework: Theory and applications to nuclear fuel behavior
Published in Nuclear engineering and design (15-08-2022)“…Nuclear fuel performance computer codes have been developed over the last 50 years to analyze fuel behavior under various operating conditions. Traditionally,…”
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