Search Results - "Gamble, Kyle A."

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  1. 1

    Modeling fission product diffusion in TRISO fuel particles with BISON by Hales, Jason D., Jiang, Wen, Toptan, Aysenur, Gamble, Kyle A.

    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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    Journal Article
  2. 2

    TRISO particle fuel performance and failure analysis with BISON by Jiang, Wen, Hales, Jason D., Spencer, Benjamin W., Collin, Blaise P., Slaughter, Andrew E., Novascone, Stephen R., Toptan, Aysenur, Gamble, Kyle A., Gardner, Russell

    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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  3. 3

    Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale by 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

    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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    Journal Article
  4. 4

    A phase-field model of quasi-brittle fracture for pressurized cracks: Application to UO2 high-burnup microstructure fragmentation by Jiang, Wen, Hu, Tianchen, Aagesen, Larry K., Biswas, Sudipta, Gamble, Kyle A.

    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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  5. 5

    Phase-field simulations of intergranular fission gas bubble behavior in U3Si2 nuclear fuel by Aagesen, Larry K., Andersson, David, Beeler, Benjamin W., Cooper, Michael W.D., Gamble, Kyle A., Miao, Yinbin, Pastore, Giovanni, Tonks, Michael R.

    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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  6. 6

    Rate theory scenarios study on fission gas behavior of U3Si2 under LOCA conditions in LWRs by Miao, Yinbin, Gamble, Kyle A., Andersson, David, Mei, Zhi-Gang, Yacout, Abdellatif M.

    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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    Comparing the impact of thermal stresses and bubble pressure on intergranular fracture in UO2 using 2D phase field fracture simulations by Zhang, Shuaifang, Jiang, Wen, Gamble, Kyle A., Tonks, Michael R.

    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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    Journal Article
  10. 10

    Modeling fission product diffusion in TRISO fuel particles with BISON by Hales, Jason D., Jiang, Wen, Toptan, Aysenur, Gamble, Kyle A.

    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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  11. 11

    Gaseous swelling of U3Si2 during steady-state LWR operation: A rate theory investigation by Miao, Yinbin, Gamble, Kyle A., Andersson, David, Ye, Bei, Mei, Zhi-Gang, Hofman, Gerard, Yacout, Abdellatif M.

    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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  12. 12

    Mechanistic verification of empirical UO2 fuel fracture models by Gamble, Kyle A., Knight, Travis W., Roberts, Elwyn, Hales, Jason D., Spencer, Benjamin W.

    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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  13. 13

    An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions by Gamble, K.A., Barani, T., Pizzocri, D., Hales, J.D., Terrani, K.A., Pastore, G.

    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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  14. 14

    Multidimensional modeling of fuel-cladding friction in an LWR fuel rod by Recuero, A.M., Gamble, K.A., Yushu, D., Lindsay, A.D.

    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 by Barani, T., Pastore, G., Pizzocri, D., Andersson, D.A., Matthews, C., Alfonsi, A., Gamble, K.A., Van Uffelen, P., Luzzi, L., Hales, J.D.

    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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  17. 17

    Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2 by Cooper, M.W.D., Gamble, K.A., Capolungo, L., Matthews, C., Andersson, D.A., Beeler, B., Stanek, C.R., Metzger, K.

    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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  18. 18

    Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale by Cooper, Michael W. D., Pastore, Giovanni, Che, Yifeng, Matthews, Christopher, Forslund, Axel, Stanek, Christopher R., Shirvan, Koroush, Tverberg, Terje, Gamble, Kyle A., Mays, Brian, Andersson, David A.

    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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    Journal Article
  19. 19

    Rate theory scenarios study on fission gas behavior of U 3 Si 2 under LOCA conditions in LWRs by Miao, Yinbin, Gamble, Kyle A., Andersson, David, Mei, Zhi-Gang, Yacout, Abdellatif M.

    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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  20. 20

    A layered 2D computational framework: Theory and applications to nuclear fuel behavior by Gamble, K.A., Spencer, B.W., Hales, J.D., Knight, T.W., Roberts, E.

    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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